{
"data": [
{
"abstract": "Abstract The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the ITER-like BeW wall. The development started in pure Deuterium with refinement of the plasma current, and toroidal magnetic field choices and succeeded in solving the heat load challenges arising from 37 MW of injected power in the ITER like wall environment, keeping the radiation in the edge and core controlled, avoiding MHD instabilities and reaching high neutron rates. The Deuterium hybrid plasmas have been re-run in Tritium and methods have been found to keep the radiation controlled but not at high fusion performance probably due to time constraints. For the first time this scenario has been run in Deuterium-Tritium 5050. These plasmas were re-optimised to have a radiation-stable H-mode entry phase, good impurity control through edge Ti gradient screening and optimised performance with fusion power exceeding 10 MW for longer than three alpha particle slow down times, 8.3 MW averaged over 5 and fusion energy of 45.8 MJ.",
"title": "The JET hybrid scenario in Deuterium, Tritium and Deuterium-Tritium",
"URL": "https://iopscience.iop.org/article/10.1088/1741-4326/acde8d/pdf",
"fields_of_study": [
"Deuterium",
"Tritium",
"Plasma",
"Fusion power",
"Materials science",
"Nuclear physics",
"Jet (fluid)",
"Neutron",
"Nuclear engineering",
"Hybrid reactor",
"Neutron generator",
"Atomic physics",
"Physics",
"Neutron source",
"Blanket",
"Mechanics",
"Engineering",
"Composite material"
],
"year_published": 2023,
"first_author": "J. Hobirk",
"scholarly_citations_count": 8,
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"category": "Chemical Element or Compound",
"entity": "Deuterium"
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"category": "Chemical Element or Compound",
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"sentence": "The development started in pure Deuterium with refinement of the plasma current, and toroidal magnetic field choices and succeeded in solving the heat load challenges arising from 37 MW of injected power in the ITER like wall environment, keeping the radiation in the edge and core controlled, avoiding MHD instabilities and reaching high neutron rates.",
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"category": "Nuclear Fusion Experimental Facility",
"entity": "ITER"
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"entity": "ITER like wall"
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{
"category": "Chemical Element or Compound",
"entity": "Deuterium"
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"category": "Plasma property",
"entity": "plasma current"
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"category": "Field Configuration",
"entity": "toroidal magnetic field"
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"category": "Plasma dynamic and behavior",
"entity": "MHD instabilities"
},
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"category": "Plasma region",
"entity": "edge"
},
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"category": "Plasma region",
"entity": "core"
}
]
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{
"sentence": "The Deuterium hybrid plasmas have been re-run in Tritium and methods have been found to keep the radiation controlled but not at high fusion performance probably due to time constraints.",
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{
"category": "Chemical Element or Compound",
"entity": "Deuterium"
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"entity": "Tritium"
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"entity": "radiation"
},
{
"category": "Plasma dynamic and behavior",
"entity": "fusion performance"
},
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"category": "Physical Process",
"entity": "radiation"
}
]
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{
"sentence": "For the first time this scenario has been run in Deuterium-Tritium 5050.",
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"category": "Chemical Element or Compound",
"entity": "Deuterium"
},
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"sentence": "These plasmas were re-optimised to have a radiation-stable H-mode entry phase, good impurity control through edge Ti gradient screening and optimised performance with fusion power exceeding 10 MW for longer than three alpha particle slow down times, 8.3 MW averaged over 5 and fusion energy of 45.8 MJ.",
"entities": [
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"category": "Plasma property",
"entity": "H-mode"
},
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},
{
"category": "Particle",
"entity": "alpha particle"
},
{
"category": "Plasma region",
"entity": "edge"
},
{
"category": "Physics Entity",
"entity": "Ti gradient"
},
{
"category": "Plasma dynamic and behavior",
"entity": "screening"
}
]
}
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{
"abstract": "The achievement of a steady ELMy H-mode phase with high ion temperature, but without a gradual rise in plasma radiation, has been a crucial point to establish high plasma performance scenarios in JET ITER-like-wall plasmas. Indeed, radiation events, due to the release of high Z impurities, such as Nickel and Copper, and W sputtered from the divertor, can strongly reduce the power crossing the plasma separatrix and slow the ELMs dynamics, thus inducing H to L transition. In particular, in JET baseline plasmas, because of the outward neoclassical transport, plasma impurities are mainly localized in the mantle region, as detected by a real-time surrogate model for bolometer tomography based on machine learning, and the consequent excessive radiation in this region is the main cause of plasma termination in recent Deuterium, Tritium and Deuterium-Tritium operations. To guarantee impurity accumulation being flushed by the ELMs, ELM control schemes, which ensure a throughput of particles, either via gas fueling and via pellets, have been exploited. In this work, the staged approach strategy towards radiation control, which allowed to sustain for more than 10 Tritium and Deuterium-Tritium baseline discharges without radiation issues, is presented.",
"title": "Radiation control in deuterium, tritium and deuterium-tritium JET baseline plasmas – part I",
"URL": "NaN",
"fields_of_study": [
"Plasma",
"Divertor",
"Deuterium",
"Joint European Torus",
"Tritium",
"Atomic physics",
"Nuclear physics",
"Impurity",
"Fusion power",
"Materials science",
"Tokamak",
"Physics",
"Nuclear engineering",
"Engineering",
"Quantum mechanics"
],
"year_published": 2023,
"first_author": "L. Piron",
"scholarly_citations_count": 7,
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"entity": "Tungsten (W)"
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"entity": "Divertor"
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"category": "Plasma property",
"entity": "ELMs (Edge-Localized Modes)"
},
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"category": "Plasma property",
"entity": "H-mode"
},
{
"category": "Plasma property",
"entity": "L-mode"
},
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"category": "Plasma event",
"entity": "H to L transition"
},
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"category": "Plasma dynamic and behavior",
"entity": "ELMs dynamics"
},
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"category": "Plasma region",
"entity": "Plasma separatrix"
}
]
},
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"sentence": "In particular, in JET baseline plasmas, because of the outward neoclassical transport, plasma impurities are mainly localized in the mantle region, as detected by a real-time surrogate model for bolometer tomography based on machine learning, and the consequent excessive radiation in this region is the main cause of plasma termination in recent Deuterium, Tritium and Deuterium-Tritium operations.",
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"category": "Nuclear Fusion Experimental Facility",
"entity": "JET"
},
{
"category": "Plasma region",
"entity": "mantle region"
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{
"category": "Detection and Monitoring Systems",
"entity": "bolometer tomography"
},
{
"category": "Software and simulation",
"entity": "real-time surrogate model for bolometer tomography based on machine learning"
},
{
"category": "Chemical Element or Compound",
"entity": "Deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "Tritium"
},
{
"category": "Plasma event",
"entity": "plasma termination"
},
{
"category": "Physical Process",
"entity": "neoclassical transport"
},
{
"category": "Plasma dynamic and behavior",
"entity": "outward neoclassical transport"
},
{
"category": "Plasma property",
"entity": "excessive radiation"
}
]
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{
"sentence": "To guarantee impurity accumulation being flushed by the ELMs, ELM control schemes, which ensure a throughput of particles, either via gas fueling and via pellets, have been exploited.",
"entities": [
{
"category": "Plasma property",
"entity": "ELMs"
},
{
"category": "Control Systems",
"entity": "ELM control schemes"
},
{
"category": "Nuclear Fusion Technique",
"entity": "gas fueling"
},
{
"category": "Nuclear Fusion Technique",
"entity": "pellets"
}
]
},
{
"sentence": "In this work, the staged approach strategy towards radiation control, which allowed to sustain for more than 10 Tritium and Deuterium-Tritium baseline discharges without radiation issues, is presented.",
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"entity": "Deuterium-Tritium"
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"entity": "radiation issues"
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"category": "Nuclear Fusion System Configuration",
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},
{
"abstract": "Converging plasma jets may be able to reach the regime of high energy density plasmas HEDP. The successful application of plasma jets to magneto-inertial fusion MIF would heat the plasma by fusion products and should increase the plasma energy density. This paper reports the results of using the University of Wisconsins 1-D Lagrangian, radiation-hydrodynamics, fusion code BUCKY to investigate two MIF converging plasma jet test cases originally analyzed by Samulyak et al.. In these cases, 15 cm or 5 cm radially thick deuterium-tritium DT plasma jets merge at 60 cm from the origin and converge radially onto a DT target magnetized to 2 T and of radius 5 cm. The BUCKY calculations reported here model these cases, starting from the time of initial contact of the jets and target. Compared to the one-temperature Samulyak et al. calculations, the one-temperature BUCKY results show similar behavior, except that the plasma radius remains about twice as long near maximum compression. One-temperature and two-temperature BUCKY results differ, reflecting the sensitivity of the calculations to timing and plasma parameter details, with the two-temperature case giving a more sustained compression.",
"title": "Compression of a spherically symmetric deuterium-tritium plasma liner onto a magnetized deuterium-tritium target",
"URL": "http://ui.adsabs.harvard.edu/abs/2012PhPl...19g2705S/abstract",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Atomic physics",
"Waves in plasmas",
"Plasma parameters",
"Two-stream instability",
"Plasma parameter",
"Magnetohydrodynamics",
"Dense plasma focus",
"Plasma"
],
"year_published": 2012,
"first_author": "J. F. Santarius",
"scholarly_citations_count": 12,
"NER-RE": [
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"sentence": "The successful application of plasma jets to magneto-inertial fusion MIF would heat the plasma by fusion products and should increase the plasma energy density.",
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"category": "Nuclear Fusion Technique",
"entity": "magneto-inertial fusion"
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"sentence": "This paper reports the results of using the University of Wisconsins 1-D Lagrangian, radiation-hydrodynamics, fusion code BUCKY to investigate two MIF converging plasma jet test cases originally analyzed by Samulyak et al..",
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"category": "Software and simulation",
"entity": "BUCKY"
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"entity": "converging plasma jet"
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"category": "Facility or Institution",
"entity": "University of Wisconsin"
},
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"category": "Person",
"entity": "Samulyak et al."
},
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"category": "Research field",
"entity": "radiation-hydrodynamics"
},
{
"category": "Research field",
"entity": "fusion"
}
]
},
{
"sentence": "In these cases, 15 cm or 5 cm radially thick deuterium-tritium DT plasma jets merge at 60 cm from the origin and converge radially onto a DT target magnetized to 2 T and of radius 5 cm.",
"entities": [
{
"category": "Nuclear Fusion System Component",
"entity": "DT target"
},
{
"category": "Field Configuration",
"entity": "magnetized to 2 T"
},
{
"category": "Chemical Element or Compound",
"entity": "deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Plasma property",
"entity": "DT plasma"
},
{
"category": "Plasma dynamic and behavior",
"entity": "merge"
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{
"category": "Plasma dynamic and behavior",
"entity": "converge radially"
}
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"sentence": "The BUCKY calculations reported here model these cases, starting from the time of initial contact of the jets and target.",
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"category": "Nuclear Fusion System Component",
"entity": "target"
},
{
"category": "Nuclear Fusion System Component",
"entity": "jets"
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"entity": "BUCKY calculations"
}
]
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{
"sentence": "Compared to the one-temperature Samulyak et al. calculations, the one-temperature BUCKY results show similar behavior, except that the plasma radius remains about twice as long near maximum compression.",
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"category": "Plasma property",
"entity": "plasma radius"
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{
"category": "Plasma property",
"entity": "maximum compression"
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"sentence": "One-temperature and two-temperature BUCKY results differ, reflecting the sensitivity of the calculations to timing and plasma parameter details, with the two-temperature case giving a more sustained compression.",
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"category": "Nuclear Fusion Technique",
"entity": "Inertial confinement fusion"
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"category": "Plasma property",
"entity": "plasma temperature"
},
{
"category": "Plasma property",
"entity": "two-temperature"
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"category": "Plasma property",
"entity": "one-temperature"
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"category": "Plasma dynamic and behavior",
"entity": "compression"
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},
{
"abstract": "During the second half of 1997, JET carried out a broad-based series of experiments in deuteriumtritium DT producing a total of 675 MJ of fusion energy and setting records for fusion power 16 MW...",
"title": "JET deuterium: tritium results and their implications",
"URL": "http://ui.adsabs.harvard.edu/abs/1999RSPTA.357..415K/abstract",
"fields_of_study": [
"Jet (fluid)",
"Physics",
"Magnetic confinement fusion",
"Lawson criterion",
"Atomic physics",
"Nuclear physics",
"Fusion power",
"Deuterium",
"Tritium"
],
"year_published": 1999,
"first_author": "M. Keilhacker",
"scholarly_citations_count": 20,
"NER-RE": [
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"sentence": "During the second half of 1997, JET carried out a broad-based series of experiments in deuteriumtritium DT producing a total of 675 MJ of fusion energy and setting records for fusion power 16 MW...",
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"category": "Nuclear Fusion Experimental Facility",
"entity": "JET"
},
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"category": "Chemical Element or Compound",
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"category": "Time reference",
"entity": "1997"
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{
"abstract": "We have investigated both theoretically and experimentally the properties of condensed DT as they apply to nuclear polarization for hydrogen fusion. At 2 K, atom densities and their electron relaxation times were found to be sufficient to pump nuclei in the process of dynamic nuclear polarization. However, the nuclear spin lattice relaxation times of both the triton and deuteron were too short by 23 orders of magnitude, as a result of the creation of rotationally excited hydrogen J1 T2 and D2 by the tritium radioactivity. Three means of lengthening these times are discussed 1 synthesizing low J1 molecular DT here, J is the molecular rotational quantum number, 2 synthesizing high J1 D2T2 in the ordered phase, and 3 placing the sub-2 K solid in fine-celled foam. The most likely method combines the first and third approaches. Even so, the purified solid DT is likely to last only 2030 min before the tritium radioactivity reduces the relaxation times. The best temperature regime is in the low-temperature solid the conditions of the solid at 1418 K and the liquid at 2123 K are not considered favorable for nuclear polarization. The first synthesis of pure DT using an adsorption column at 23 K is demonstrated.",
"title": "Nuclear polarization of solid deuterium–tritium",
"URL": "NaN",
"fields_of_study": [
"Deuterium",
"Tritium",
"Hydrogen",
"Solid hydrogen",
"Polarization (electrochemistry)",
"Excited state",
"Nuclear fusion",
"Chemistry",
"Spin isomers of hydrogen",
"Atomic physics",
"Adsorption",
"Analytical Chemistry (journal)",
"Physical chemistry",
"Nuclear physics",
"Physics",
"Chromatography",
"Organic chemistry"
],
"year_published": 1993,
"first_author": "P. C. Souers",
"scholarly_citations_count": 4,
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"entity": "hydrogen fusion"
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"sentence": "At 2 K, atom densities and their electron relaxation times were found to be sufficient to pump nuclei in the process of dynamic nuclear polarization.",
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"sentence": "However, the nuclear spin lattice relaxation times of both the triton and deuteron were too short by 23 orders of magnitude, as a result of the creation of rotationally excited hydrogen J1 T2 and D2 by the tritium radioactivity.",
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"category": "Particle",
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"sentence": "The most likely method combines the first and third approaches.",
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"sentence": "Even so, the purified solid DT is likely to last only 2030 min before the tritium radioactivity reduces the relaxation times.",
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"sentence": "The first synthesis of pure DT using an adsorption column at 23 K is demonstrated.",
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"entity": "DT"
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{
"category": "Experimental Apparatus",
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},
{
"abstract": "The Tokamak Fusion Test Reactor TFTR has performed initial high-power experiments with the plasma fueled by deuterium and tritium to nominally equal densities. Compared to pure deuterium plasmas, the energy stored in the electron and ions increased by 20. These increases indicate improvements in confinement associated with the use of tritium and possibly heating of electrons by α-particles.",
"title": "Confinement and heating of a deuterium-tritium plasma.",
"URL": "https://inis.iaea.org/Search/search.aspx?orig_q=RN:25060631",
"fields_of_study": [
"Physics",
"Ion",
"Lawson criterion",
"Atomic physics",
"Electron temperature",
"Tokamak Fusion Test Reactor",
"Plasma diagnostics",
"Deuterium",
"Tritium",
"Plasma"
],
"year_published": 1994,
"first_author": "R. J. Hawryluk",
"scholarly_citations_count": 90,
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},
{
"category": "Physical Process",
"entity": "confinement"
}
]
}
]
},
{
"abstract": "A transport code TRANSP is used to simulate future deuterium-tritium DT experiments in TFTR. The simulations are derived from 14 TFTR DD discharges, and the modelling of one supershot is discussed in detail to indicate the degree of accuracy of the TRANSP modelling. Fusion energy yields and alpha particle parameters are calculated, including profiles of the alpha slowing down time, the alpha average energy, and the Alfven speed and frequency. Two types of simulation are discussed. The main emphasis is on the DT equivalent, where an equal mix of D and T is substituted for the D in the initial target plasma, and for the D0 in the neutral beam injection, but the other measured beam and plasma parameters are unchanged. This simulation does not assume that alpha heating will enhance the plasma parameters or that confinement will increase with the addition of tritium. The maximum relative fusion yield calculated for these simulations is QDT 0.3, and the maximum alpha contribution to the central toroidal β is βα0 0.5. The stability of toroidicity induced Alfven eigenmodes TAE and kinetic ballooning modes KBM is discussed. The TAE mode is predicted to become unstable for some of the simulations, particularly after the termination of neutral beam injection. In the second type of simulation, empirical supershot scaling relations are used to project the performance at the maximum expected beam power. The MHD stability of the simulations is discussed",
"title": "Simulations of deuterium-tritium experiments in TFTR",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/32/3/I07/meta",
"fields_of_study": [
"Physics",
"Kinetic energy",
"Beam (structure)",
"Nuclear physics",
"Plasma parameters",
"Fusion power",
"Neutral beam injection",
"Magnetohydrodynamics",
"Alpha particle",
"Plasma"
],
"year_published": 1992,
"first_author": "Robert Budny",
"scholarly_citations_count": 165,
"NER-RE": [
{
"sentence": "A transport code TRANSP is used to simulate future deuterium-tritium DT experiments in TFTR.",
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"category": "Software and simulation",
"entity": "TRANSP"
},
{
"category": "Chemical Element or Compound",
"entity": "Deuterium"
},
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"entity": "Tritium"
},
{
"category": "Nuclear Fusion Experimental Facility",
"entity": "TFTR"
}
]
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"category": "Nuclear Fusion Experimental Facility",
"entity": "TFTR"
},
{
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"entity": "Tokamak"
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"entity": "supershot"
},
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}
]
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"sentence": "Fusion energy yields and alpha particle parameters are calculated, including profiles of the alpha slowing down time, the alpha average energy, and the Alfven speed and frequency.",
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"entity": "Alfven speed"
},
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"category": "Physics Entity",
"entity": "Alfven frequency"
},
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"category": "Particle",
"entity": "alpha particle"
},
{
"category": "Theory and Calculation",
"entity": "Fusion energy yields"
}
]
},
{
"sentence": "Two types of simulation are discussed.",
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"category": "Concept",
"entity": "simulation"
}
]
},
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{
"category": "Nuclear Fusion System Component",
"entity": "target plasma"
},
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"category": "Nuclear Fusion System Component",
"entity": "neutral beam injection"
},
{
"category": "Particle",
"entity": "D"
},
{
"category": "Chemical Element or Compound",
"entity": "T"
},
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"category": "Chemical Element or Compound",
"entity": "DT"
},
{
"category": "Plasma property",
"entity": "D0"
}
]
},
{
"sentence": "This simulation does not assume that alpha heating will enhance the plasma parameters or that confinement will increase with the addition of tritium.",
"entities": [
{
"category": "Plasma property",
"entity": "alpha heating"
},
{
"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Plasma property",
"entity": "confinement"
},
{
"category": "Software and simulation",
"entity": "simulation"
}
]
},
{
"sentence": "The maximum relative fusion yield calculated for these simulations is QDT 0.3, and the maximum alpha contribution to the central toroidal β is βα0 0.5.",
"entities": [
{
"category": "Plasma property",
"entity": "toroidal β"
},
{
"category": "Physics Entity",
"entity": "QDT"
},
{
"category": "Particle",
"entity": "alpha"
},
{
"category": "Theory and Calculation",
"entity": "central toroidal β"
},
{
"category": "Theory and Calculation",
"entity": "fusion yield"
}
]
},
{
"sentence": "The stability of toroidicity induced Alfven eigenmodes TAE and kinetic ballooning modes KBM is discussed.",
"entities": [
{
"category": "Plasma dynamic and behavior",
"entity": "toroidicity induced Alfven eigenmodes"
},
{
"category": "Plasma dynamic and behavior",
"entity": "kinetic ballooning modes"
},
{
"category": "Concept",
"entity": "Alfven eigenmodes"
},
{
"category": "Concept",
"entity": "kinetic ballooning modes"
}
]
},
{
"sentence": "The TAE mode is predicted to become unstable for some of the simulations, particularly after the termination of neutral beam injection.",
"entities": [
{
"category": "Plasma property",
"entity": "TAE mode"
},
{
"category": "Experimental Apparatus",
"entity": "neutral beam injection"
},
{
"category": "Plasma event",
"entity": "termination of neutral beam injection"
},
{
"category": "Software and simulation",
"entity": "simulations"
}
]
},
{
"sentence": "In the second type of simulation, empirical supershot scaling relations are used to project the performance at the maximum expected beam power.",
"entities": [
{
"category": "Software and simulation",
"entity": "empirical supershot scaling relations"
},
{
"category": "Nuclear Fusion System Component",
"entity": "beam"
}
]
},
{
"sentence": "The MHD stability of the simulations is discussed",
"entities": [
{
"category": "Plasma dynamic and behavior",
"entity": "MHD stability"
},
{
"category": "Software and simulation",
"entity": "simulations"
}
]
}
]
},
{
"abstract": "For the first time, quantitative measurements of collective fuel velocities in Inertial Confinement Fusion implosions at the National Ignition Facility are reported. Velocities along the line-of-sight LOS of the Magnetic Recoil neutron Spectrometer MRS, positioned close to the equator 73324, were inferred from the measured mean energy of the deuterium-tritium DT-primary neutron peak. Substantial mean energy shifts up to 113 16 keV were observed in DT gas-filled exploding-pusher implosions, driven in a polar-direct drive configuration, which corresponds to bulk fuel velocities up to 210 30 kms. In contrast, only marginal bulk fuel velocities along the MRS LOS were observed in cryogenically layered DT implosions. Integrated analysis of data from a large number of cryogenically layered implosions has recently identified a deficit in achieved hot-spot energy of 3 kJ for these implosions. One hypothesis that could explain this missing energy is a collective, directional fuel velocity of 190 kms. As only marginal bulk fuel velocities are observed in the MRS data, this might indicate that turbulent or radial flows would be a likely explanation for the missing energy. However, a directional velocity close to perpendicular to the MRS LOS cannot be ruled out.",
"title": "Measurements of collective fuel velocities in deuterium-tritium exploding pusher and cryogenically layered deuterium-tritium implosions on the NIF",
"URL": "https://ui.adsabs.harvard.edu/abs/2013PhPl...20d2707G/abstract",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Neutron",
"Atomic physics",
"Nuclear physics",
"Turbulence",
"Recoil",
"National Ignition Facility",
"Plasma diagnostics",
"Deuterium",
"Plasma"
],
"year_published": 2013,
"first_author": "M. Gatu Johnson",
"scholarly_citations_count": 43,
"NER-RE": [
{
"sentence": "For the first time, quantitative measurements of collective fuel velocities in Inertial Confinement Fusion implosions at the National Ignition Facility are reported.",
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{
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"entity": "National Ignition Facility"
},
{
"category": "Nuclear Fusion Technique",
"entity": "Inertial Confinement Fusion"
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{
"category": "Physical Process",
"entity": "implosions"
},
{
"category": "Physics Entity",
"entity": "collective fuel velocities"
}
]
},
{
"sentence": "Velocities along the line-of-sight LOS of the Magnetic Recoil neutron Spectrometer MRS, positioned close to the equator 73324, were inferred from the measured mean energy of the deuterium-tritium DT-primary neutron peak.",
"entities": [
{
"category": "Nuclear Fusion Device Type",
"entity": "Magnetic Recoil neutron Spectrometer"
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{
"category": "Experimental Apparatus",
"entity": "MRS"
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{
"category": "Particle",
"entity": "deuterium-tritium"
},
{
"category": "Particle",
"entity": "neutron"
},
{
"category": "Plasma property",
"entity": "mean energy"
},
{
"category": "Detection and Monitoring Systems",
"entity": "Spectrometer"
},
{
"category": "Nuclear Fusion System Component",
"entity": "LOS"
},
{
"category": "Location",
"entity": "equator"
}
]
},
{
"sentence": "Substantial mean energy shifts up to 113 16 keV were observed in DT gas-filled exploding-pusher implosions, driven in a polar-direct drive configuration, which corresponds to bulk fuel velocities up to 210 30 kms.",
"entities": [
{
"category": "Nuclear Fusion Technique",
"entity": "polar-direct drive"
},
{
"category": "Nuclear Fusion System Configuration",
"entity": "exploding-pusher implosions"
},
{
"category": "Plasma property",
"entity": "bulk fuel velocities"
},
{
"category": "Chemical Element or Compound",
"entity": "DT gas"
}
]
},
{
"sentence": "In contrast, only marginal bulk fuel velocities along the MRS LOS were observed in cryogenically layered DT implosions.",
"entities": [
{
"category": "Nuclear Fusion Technique",
"entity": "cryogenically layered DT implosions"
},
{
"category": "Detection and Monitoring Systems",
"entity": "MRS LOS"
},
{
"category": "Physics Entity",
"entity": "bulk fuel velocities"
},
{
"category": "Chemical Element or Compound",
"entity": "DT"
}
]
},
{
"sentence": "Integrated analysis of data from a large number of cryogenically layered implosions has recently identified a deficit in achieved hot-spot energy of 3 kJ for these implosions.",
"entities": [
{
"category": "Nuclear Fusion Technique",
"entity": "cryogenically layered implosions"
},
{
"category": "Plasma region",
"entity": "hot-spot"
},
{
"category": "Physics Entity",
"entity": "hot-spot energy"
}
]
},
{
"sentence": "One hypothesis that could explain this missing energy is a collective, directional fuel velocity of 190 kms.",
"entities": [
{
"category": "Physics Entity",
"entity": "fuel velocity"
},
{
"category": "Concept",
"entity": "hypothesis"
}
]
},
{
"sentence": "As only marginal bulk fuel velocities are observed in the MRS data, this might indicate that turbulent or radial flows would be a likely explanation for the missing energy.",
"entities": [
{
"category": "Plasma dynamic and behavior",
"entity": "turbulent flows"
},
{
"category": "Plasma dynamic and behavior",
"entity": "radial flows"
},
{
"category": "Detection and Monitoring Systems",
"entity": "MRS data"
},
{
"category": "Physics Entity",
"entity": "bulk fuel velocities"
},
{
"category": "Physics Entity",
"entity": "energy"
}
]
},
{
"sentence": "However, a directional velocity close to perpendicular to the MRS LOS cannot be ruled out.",
"entities": [
{
"category": "Physics Entity",
"entity": "velocity"
},
{
"category": "Physics Entity",
"entity": "LOS (Line of Sight)"
},
{
"category": "Nuclear Fusion System Component",
"entity": "MRS (Magnetic Resonance Spectroscopy)"
}
]
}
]
},
{
"abstract": "Measurements of the ion currents to and plasma conditions at the low-field side LFS divertor target plate in low-confinement mode plasmas in the JET ITER-like wall materials configuration show that the core plasma density required to detach the LFS divertor plasma is independent of the hydrogenic species protium, deuterium and tritium, and a 40 60 deuteriumtritium mixture. This observation applies to a divertor plasma configuration with the LFS strike line connected to the horizontal part of the LFS divertor chosen because of its superior diagnostic coverage. The finding is independent of the operational status of the JET cryogenic pump. The electron temperature Te at the LFS strike line was markedly reduced from 25 eV to 5 eV over a narrow range of increasing core plasma density, and observed to be between 2 eV and 3 eV at the onset of detachment. The electron density ne peaks across the LFS plasma when Te at the target plate is 1 eV, and spatially moves to the X-point for higher core densities. The density limit was found approximately 20 higher in protium than in tritium and deuteriumtritium plasmas.",
"title": "Characterisation of divertor detachment onset in JET-ILW hydrogen, deuterium, tritium and deuterium–tritium low-confinement mode plasmas",
"URL": "https://research.aalto.fi/files/97748118/Characterisation_of_divertor_detachment_onset_in_JET_ILW_hydrogen_deuterium_tritium_and_deuterium_tritium_low_confinement_mode_plasmas.pdf",
"fields_of_study": [
"Divertor",
"Deuterium",
"Tritium",
"Plasma",
"Atomic physics",
"Hydrogen",
"Jet (fluid)",
"Chemistry",
"Nuclear physics",
"Tokamak",
"Physics",
"Organic chemistry",
"Thermodynamics"
],
"year_published": 2023,
"first_author": "M. Groth",
"scholarly_citations_count": 3,
"NER-RE": [
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"sentence": "Measurements of the ion currents to and plasma conditions at the low-field side LFS divertor target plate in low-confinement mode plasmas in the JET ITER-like wall materials configuration show that the core plasma density required to detach the LFS divertor plasma is independent of the hydrogenic species protium, deuterium and tritium, and a 40 60 deuteriumtritium mixture.",
"entities": [
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"category": "Nuclear Fusion Experimental Facility",
"entity": "JET"
},
{
"category": "Nuclear Fusion Device Type",
"entity": "ITER-like wall"
},
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"category": "Chemical Element or Compound",
"entity": "deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Chemical Element or Compound",
"entity": "protium"
},
{
"category": "Plasma property",
"entity": "low-confinement mode"
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"category": "Plasma region",
"entity": "core plasma"
},
{
"category": "Plasma region",
"entity": "LFS divertor plasma"
},
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"category": "Nuclear Fusion System Component",
"entity": "divertor target plate"
},
{
"category": "Nuclear Fusion System Configuration",
"entity": "JET ITER-like wall materials configuration"
}
]
},
{
"sentence": "This observation applies to a divertor plasma configuration with the LFS strike line connected to the horizontal part of the LFS divertor chosen because of its superior diagnostic coverage.",
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{
"category": "Nuclear Fusion System Component",
"entity": "Divertor"
},
{
"category": "Nuclear Fusion System Configuration",
"entity": "Divertor plasma configuration"
},
{
"category": "Plasma region",
"entity": "LFS strike line"
},
{
"category": "Plasma region",
"entity": "LFS strike line"
},
{
"category": "Nuclear Fusion System Component",
"entity": "LFS divertor"
}
]
},
{
"sentence": "The finding is independent of the operational status of the JET cryogenic pump.",
"entities": [
{
"category": "Nuclear Fusion Experimental Facility",
"entity": "JET"
},
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"category": "Experimental Apparatus",
"entity": "cryogenic pump"
}
]
},
{
"sentence": "The electron temperature Te at the LFS strike line was markedly reduced from 25 eV to 5 eV over a narrow range of increasing core plasma density, and observed to be between 2 eV and 3 eV at the onset of detachment.",
"entities": [
{
"category": "Plasma property",
"entity": "electron temperature"
},
{
"category": "Plasma region",
"entity": "LFS strike line"
},
{
"category": "Plasma region",
"entity": "core plasma density"
},
{
"category": "Plasma event",
"entity": "onset of detachment"
}
]
},
{
"sentence": "The electron density ne peaks across the LFS plasma when Te at the target plate is 1 eV, and spatially moves to the X-point for higher core densities.",
"entities": [
{
"category": "Plasma property",
"entity": "electron density"
},
{
"category": "Physics Entity",
"entity": "Te"
},
{
"category": "Nuclear Fusion System Component",
"entity": "target plate"
},
{
"category": "Plasma region",
"entity": "LFS plasma"
},
{
"category": "Plasma region",
"entity": "X-point"
},
{
"category": "Plasma property",
"entity": "core densities"
}
]
},
{
"sentence": "The density limit was found approximately 20 higher in protium than in tritium and deuteriumtritium plasmas.",
"entities": [
{
"category": "Chemical Element or Compound",
"entity": "protium"
},
{
"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Chemical Element or Compound",
"entity": "deuterium"
},
{
"category": "Plasma property",
"entity": "deuterium-tritium plasmas"
},
{
"category": "Plasma property",
"entity": "density limit"
}
]
}
]
},
{
"abstract": "We have investigated both theoretically and experimentally the properties of condensed DT as they apply to nuclear polarization for hydrogen fusion. At 2 K, atom densities and their electron relaxation times were found to be sufficient to pump nuclei in the process of dynamic nuclear polarization. However, the nuclear spin lattice relaxation times of both the triton and deuteron were too short by 23 orders of magnitude, as a result of the creation of rotationally excited hydrogen J1 T2 and D2 by the tritium radioactivity. Three means of lengthening these times are discussed 1 synthesizing low J1 molecular DT here, J is the molecular rotational quantum number, 2 synthesizing high J1 D2T2 in the ordered phase, and 3 placing the sub2 K solid in finecelled foam. The most likely method combines the first and third approaches. Even so, the purified solid DT is likely to last only 2030 min before the tritium radioactivity reduces the relaxation times. The best temperature regime is in the lowtemperature solid the conditions of the solid at 1418 K and the liquid at 2123 K are not considered favorable for nuclear polarization. The first synthesis of pure DT using an adsorption column at 23 K is demonstrated.",
"title": "Nuclear spin polarization of solid deuterium--tritium",
"URL": "http://ui.adsabs.harvard.edu/abs/1986JVSTA...4.1118S/abstract",
"fields_of_study": [
"Quantum number",
"Excited state",
"Atomic physics",
"Nuclear physics",
"Chemistry",
"Nuclear reaction",
"Relaxation (NMR)",
"Hydrogen",
"Deuterium",
"Tritium",
"Impurity"
],
"year_published": 1986,
"first_author": "P. C. Souers",
"scholarly_citations_count": 10,
"NER-RE": [
{
"sentence": "We have investigated both theoretically and experimentally the properties of condensed DT as they apply to nuclear polarization for hydrogen fusion.",
"entities": [
{
"category": "Chemical Element or Compound",
"entity": "DT"
},
{
"category": "Concept",
"entity": "nuclear polarization"
},
{
"category": "Concept",
"entity": "hydrogen fusion"
}
]
},
{
"sentence": "At 2 K, atom densities and their electron relaxation times were found to be sufficient to pump nuclei in the process of dynamic nuclear polarization.",
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{
"category": "Physical Process",
"entity": "dynamic nuclear polarization"
},
{
"category": "Physics Entity",
"entity": "atom densities"
},
{
"category": "Physics Entity",
"entity": "electron relaxation times"
},
{
"category": "Particle",
"entity": "nuclei"
},
{
"category": "Particle",
"entity": "electron"
}
]
},
{
"sentence": "However, the nuclear spin lattice relaxation times of both the triton and deuteron were too short by 23 orders of magnitude, as a result of the creation of rotationally excited hydrogen J1 T2 and D2 by the tritium radioactivity.",
"entities": [
{
"category": "Particle",
"entity": "triton"
},
{
"category": "Particle",
"entity": "deuteron"
},
{
"category": "Chemical Element or Compound",
"entity": "hydrogen"
},
{
"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Physical Process",
"entity": "nuclear spin lattice relaxation"
},
{
"category": "Physics Entity",
"entity": "rotationally excited hydrogen J1 T2 and D2"
},
{
"category": "Physics Entity",
"entity": "radioactivity"
}
]
},
{
"sentence": "Three means of lengthening these times are discussed 1 synthesizing low J1 molecular DT here, J is the molecular rotational quantum number, 2 synthesizing high J1 D2T2 in the ordered phase, and 3 placing the sub2 K solid in finecelled foam.",
"entities": [
{
"category": "Chemical Element or Compound",
"entity": "DT"
},
{
"category": "Chemical Element or Compound",
"entity": "D2T2"
},
{
"category": "Chemical Element or Compound",
"entity": "D2"
},
{
"category": "Physics Entity",
"entity": "J1 molecular rotational quantum number"
},
{
"category": "Physics Entity",
"entity": "sub2 K solid"
},
{
"category": "Experimental Apparatus",
"entity": "fine-celled foam"
}
]
},
{
"sentence": "The most likely method combines the first and third approaches.",
"entities": [
{
"category": "Nuclear Fusion Technique",
"entity": "first approach"
},
{
"category": "Nuclear Fusion Technique",
"entity": "third approach"
},
{
"category": "Concept",
"entity": "method"
}
]
},
{
"sentence": "Even so, the purified solid DT is likely to last only 2030 min before the tritium radioactivity reduces the relaxation times.",
"entities": [
{
"category": "Chemical Element or Compound",
"entity": "Tritium"
},
{
"category": "Physics Entity",
"entity": "Radioactivity"
},
{
"category": "Physical Process",
"entity": "Relaxation times"
}
]
},
{
"sentence": "The best temperature regime is in the lowtemperature solid the conditions of the solid at 1418 K and the liquid at 2123 K are not considered favorable for nuclear polarization.",
"entities": [
{
"category": "Physics Entity",
"entity": "temperature"
},
{
"category": "Physics Entity",
"entity": "solid"
},
{
"category": "Physics Entity",
"entity": "liquid"
},
{
"category": "Plasma property",
"entity": "nuclear polarization"
},
{
"category": "Physical Process",
"entity": "polarization"
}
]
},
{
"sentence": "The first synthesis of pure DT using an adsorption column at 23 K is demonstrated.",
"entities": [
{
"category": "Chemical Element or Compound",
"entity": "DT"
},
{
"category": "Experimental Apparatus",
"entity": "adsorption column"
}
]
}
]
},
{
"abstract": "In order to achieve the self-sustaining fusion goal of inertial confinement fusion ICF, extremely strict requirements for the quality of deuterium-tritiumD-T ice in the target shell have been put forward. The concentricity between the inner surface of the ice and the target shell is required to be greater than 99.9, and the root mean square RMS roughness of the inner surface of the ice is better than 1 μm. The high-quality ICF target is based on the high-quality D-T ice in the target shell. Single crystal is the best form of D-T ice, and seed crystal in target shell is the basic condition. In this paper, the step temperature control method of gradually reducing the heating rate is used to study the retention of seed crystals in the fill tube, and the nucleation mechanism of retention of seed crystals in the fill tube is revealed. The experimental results show that the use of the fill tube defects can keep stable and single seed crystal, and under the same supercooling, when deuterium tritium seed crystal ltigtcltigt-axis and the fill tube are axially parallel, the growth rate is about 12 orders of magnitude slower than that when the ltigtcltigt-axis is perpendicular to the axial direction of the gas filled tube. The results provide a reference for obtaining high-quality seed crystals, and a basic support for developing the D-T target in China.",
"title": "Crystal nucleation behavior of deuterium tritium ice",
"URL": "https://wulixb.iphy.ac.cn/pdf-content/10.7498/aps.71.20211018.pdf",
"fields_of_study": [
"Nucleation",
"Supercooling",
"Deuterium",
"Materials science",
"Tritium",
"Crystal (programming language)",
"Ice crystals",
"Inertial confinement fusion",
"Seed crystal",
"Precipitation",
"Surface roughness",
"Crystallography",
"Single crystal",
"Composite material",
"Atomic physics",
"Optics",
"Physics",
"Nuclear physics",
"Meteorology",
"Chemistry",
"Thermodynamics",
"Laser",
"Computer science",
"Programming language"
],
"year_published": 2022,
"first_author": "Wei-Guang Zhang",
"scholarly_citations_count": "NaN",
"NER-RE": [
{
"sentence": "In order to achieve the self-sustaining fusion goal of inertial confinement fusion ICF, extremely strict requirements for the quality of deuterium-tritiumD-T ice in the target shell have been put forward.",
"entities": [
{
"category": "Nuclear Fusion Technique",
"entity": "Inertial Confinement Fusion"
},
{
"category": "Chemical Element or Compound",
"entity": "Deuterium-Tritium"
},
{
"category": "Nuclear Fusion System Component",
"entity": "Target Shell"
},
{
"category": "Chemical Element or Compound",
"entity": "Deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "Tritium"
},
{
"category": "Nuclear Fusion System Component",
"entity": "D-T ice"
}
]
},
{
"sentence": "The concentricity between the inner surface of the ice and the target shell is required to be greater than 99.9, and the root mean square RMS roughness of the inner surface of the ice is better than 1 μm.",
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{
"category": "Nuclear Fusion System Component",
"entity": "target shell"
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"entity": "root mean square RMS roughness"
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"category": "Physics Entity",
"entity": "concentricity"
}
]
},
{
"sentence": "The high-quality ICF target is based on the high-quality D-T ice in the target shell.",
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{
"category": "Nuclear Fusion System Component",
"entity": "target shell"
},
{
"category": "Chemical Element or Compound",
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},
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"category": "Nuclear Fusion System Component",
"entity": "ICF target"
}
]
},
{
"sentence": "Single crystal is the best form of D-T ice, and seed crystal in target shell is the basic condition.",
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{
"category": "Nuclear Fusion System Component",
"entity": "target shell"
},
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"category": "Physics Entity",
"entity": "single crystal"
},
{
"category": "Physics Entity",
"entity": "seed crystal"
}
]
},
{
"sentence": "The results provide a reference for obtaining high-quality seed crystals, and a basic support for developing the D-T target in China.",
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{
"category": "Nuclear Fusion System Component",
"entity": "D-T target"
},
{
"category": "Country and location",
"entity": "China"
}
]
}
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},
{
"abstract": "Deuterium-tritium fusion neutrons, peaked at 14.1 MeV, can activate the materials employed in a fusion reactor. The radioactivation characteristics and level of activation that occurs in a fusion reactor after shutdown depend on the elements that are activated, the neutron wall loading, the duration of the exposure, and the neutron flux spectrum present. The radioactivity resulting from potential elements considered in fusion reactor designs is discussed. The dominating radionuclides and the levels of activation resulting from exposure of these elements to the neutron flux spectrum in the first-wall region of a typical Lisub 2O solid-breeder fusion reactor blanket are also given.",
"title": "Radioactivation characteristics for deuterium-tritium fusion reactors",
"URL": "http://www.osti.gov/scitech/biblio/6782703-radioactivation-characteristics-deuterium-tritium-fusion-reactors",
"fields_of_study": [
"Activation product",
"Neutron",
"Radiochemistry",
"Chemistry",
"Fusion power",
"Neutron cross section",
"Deuterium",
"Tritium",
"Radiation flux",
"Neutron flux"
],
"year_published": 1983,
"first_author": "E. T. Cheng",
"scholarly_citations_count": 3,
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{
"abstract": "Adaptive-mesh-refinement hydrodynamic simulations have been performed of cross sections of fibrous foams saturated with cryogenic deuterium and tritium DT. Material tracking indicates that the fibers and DT mix rapidly behind the shock. In addition, fluctuation decay lengths are on the order of a micron even in the absence of radiative and thermal energy transport. Outside the mix region, the RankineHugoniot equations are satisfied to the degree to which the turbulence and transverse motion decay, a few percent or less. Simulations also show that the shock-front perturbations decay rapidly after the shock leaves the foam and enters a layer of DT ice, suggesting that the foam microstructure will not contribute to feedthrough.",
"title": "Shock propagation in deuterium-tritium-saturated foam",
"URL": "https://ui.adsabs.harvard.edu/abs/2005PhPl...12f2705C/abstract",
"fields_of_study": [
"Thermal energy",
"Physics",
"Transverse plane",
"Atomic physics",
"Turbulence",
"Mechanics",
"Deuterium",
"Shock wave",
"Radiative transfer",
"Plasma",
"Shock (mechanics)"
],
"year_published": 2005,
"first_author": "T. J. B. Collins",
"scholarly_citations_count": 26,
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"sentence": "Simulations also show that the shock-front perturbations decay rapidly after the shock leaves the foam and enters a layer of DT ice, suggesting that the foam microstructure will not contribute to feedthrough.",
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"entity": "Simulations"
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]
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{
"abstract": "Ignition characteristics in deuterium-tritium helical stellarator reactors of various sizes are studied with the operation path method on the plane and the POPCON method. Based on empirical large...",
"title": "Ignition characteristics in deuterium-tritium helical reactors",
"URL": "https://www.ans.org/pubs/journals/fst/a_30358",
"fields_of_study": [
"Physics",
"Ignition system",
"Stellarator",
"Scaling law",
"Mechanics",
"Deuterium",
"Tritium"
],
"year_published": 1995,
"first_author": "Osamu Mitarai",
"scholarly_citations_count": 2,
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"entity": "helical stellarator"
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"entity": "deuterium"
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"category": "Chemical Element or Compound",
"entity": "tritium"
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"entity": "operation path method"
},
{
"category": "Nuclear Fusion Technique",
"entity": "POPCON method"
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]
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{
"abstract": "Evidence for fusion heating in the core of a deuterium-tritium D-T tokamak plasma is reported for the first time. Electron temperature profile data were analyzed for differences between D-T, D, and T plasmas in the Tokamak Fusion Test Reactor. Data from D and D-T plasmas with similar plasma parameters were averaged to minimize isotopic effects. The electron temperature in D-T plasmas was systematically higher than in D or T plasmas. The temperature difference between D-T and D plasmas with similar confinement times is consistent with alpha-particle heating of electrons.",
"title": "Fusion heating in a deuterium-tritium tokamak plasma.",
"URL": "https://ui.adsabs.harvard.edu/abs/1996PhRvL..76.2722T/abstract",
"fields_of_study": [
"Tokamak",
"Magnetic confinement fusion",
"Lawson criterion",
"Atomic physics",
"Plasma parameters",
"Materials science",
"Electron temperature",
"Fusion power",
"Tokamak Fusion Test Reactor",
"Plasma"
],
"year_published": 1996,
"first_author": "G. Taylor",
"scholarly_citations_count": 48,
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"entity": "Tokamak"
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"sentence": "Electron temperature profile data were analyzed for differences between D-T, D, and T plasmas in the Tokamak Fusion Test Reactor.",
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"category": "Nuclear Fusion Device Type",
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"sentence": "The temperature difference between D-T and D plasmas with similar confinement times is consistent with alpha-particle heating of electrons.",
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"category": "Particle",
"entity": "alpha-particle"
},
{
"category": "Particle",
"entity": "electrons"
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{
"category": "Plasma property",
"entity": "temperature difference"
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{
"category": "Plasma dynamic and behavior",
"entity": "alpha-particle heating"
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{
"category": "Plasma dynamic and behavior",
"entity": "confinement times"
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"category": "Plasma type",
"entity": "D-T plasma"
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{
"category": "Plasma type",
"entity": "D plasma"
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{
"abstract": "Deuterium-tritium fusion neutrons, peaked at 14.1 MeV, can activate the materials employed in a fusion reactor. The radioactivation characteristics and level of activation that occurs in a fusion ...",
"title": "Radioactivation characteristics for deuterium-tritium fusion reactors",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST83-A22806",
"fields_of_study": [
"Activation product",
"Neutron",
"Nuclear physics",
"Materials science",
"Fusion power",
"Neutron cross section",
"Deuterium",
"Tritium",
"Radiation flux",
"Neutron flux"
],
"year_published": 1983,
"first_author": "E. T. Cheng",
"scholarly_citations_count": 4,
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{
"abstract": "It appears that parallel alignment of deuteron and triton magnetic moments increases the cross section of the nuclear reaction Td, He4 by 50, thereby promising a laser driver of perhaps half the original energy. Both brute-force and dynamic nuclear polarization are considered and the many potential problems of the latter are considered. High nuclear polarization by the dynamic technique requires a small nucleus-to-unpaired electron ratio, a long longitudinal nuclear relaxation time and a short longitudinal electron relaxation time. Normal DT is shown to be inadequate, and enriched and possibly very pure molecular DT will be required. The key variable is the nuclear relaxation time, which can either depend on the interaction with rotationally excited impurity molecules or on paramagnetic defects formed by the tritium radiation. Radiation-induced DT decomposition and rotational catalysis will combat one another to affect the DT purity. The expected atom density and fractionation effects are considered. There exists one frequency at which both D and T atoms can be pumped.",
"title": "Nuclear spin polarization of solid deuterium–tritium",
"URL": "NaN",
"fields_of_study": "NaN",
"year_published": 1986,
"first_author": "P. C. Souers",
"scholarly_citations_count": 10,
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"sentence": "High nuclear polarization by the dynamic technique requires a small nucleus-to-unpaired electron ratio, a long longitudinal nuclear relaxation time and a short longitudinal electron relaxation time.",
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"sentence": "Radiation-induced DT decomposition and rotational catalysis will combat one another to affect the DT purity.",
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"entity": "DT purity"
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{
"abstract": "The Bremsstrahlung radiation power is one of the important loss processes in the inertial confinement fusion. The motion of ions is usually neglected when calculating the Bremsstrahlung radiation of the plasma. We calculate the Bremsstrahlung radiation power by taking into account the motion of ions in degenerate plasma. We found a two-temperature function for Bremsstrahlung radiation of the plasma. Finally, the Bremsstrahlung optical depth is obtained for plasma.",
"title": "BREMSSTRAHLUNG RADIATION IN DEUTERIUM/TRITIUM DEGENERATE PLASMA",
"URL": "https://www.worldscientific.com/doi/10.1142/S0217984910025231",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Ion",
"Atomic physics",
"Nuclear physics",
"Maxwell–Boltzmann distribution",
"Fermi energy",
"Fermi–Dirac statistics",
"Deuterium",
"Bremsstrahlung",
"Plasma"
],
"year_published": 2010,
"first_author": "Mohammad Mahdavi",
"scholarly_citations_count": 2,
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"sentence": "Finally, the Bremsstrahlung optical depth is obtained for plasma.",
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{
"abstract": "An escaping alpha collector probe has been developed for the deuterium-tritium DT phase of the Tokamak Fusion Test Reactor TFTR to complement the results of the lost alpha scintillator detectors, which have been operating on TFTR since 1988. Measurements of the energy distribution of escaping alphas have been made by measuring the range of alphas implanted into nickel foils located within the alpha collector. Exposed samples have been analysed for four DT plasma discharges at plasma currents of 1.0 and 1.8 MA. The results at 1.0 MA are in good agreement with predictions for first orbit alpha loss at 3.5 MeV. The 1.8 MA results, however, indicate a large anomalous loss of partially thermalized alphas at an energy 30 below the birth energy and at a total fluence nearly an order of magnitude above the expected first orbit loss. This anomalous loss is not observed with the lost alpha scintillator detectors in DT plasmas but does resemble the anomalous delayed loss seen in DD plasmas. Several potential explanations for this loss process are examined. None of the candidate explanations proposed thus far are fully consistent with the anomalous loss observations",
"title": "Deuterium-tritium results of TFTR's alpha collector",
"URL": "https://pure.mpg.de/pubman/faces/ViewItemOverviewPage.jsp?itemId=item_2158587",
"fields_of_study": [
"Physics",
"Order of magnitude",
"Scintillator",
"Nuclear physics",
"Fluence",
"Tokamak Fusion Test Reactor",
"Range (particle radiation)",
"Deuterium",
"Tritium",
"Plasma"
],
"year_published": 1997,
"first_author": "H. W. Herrmann",
"scholarly_citations_count": 16,
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"sentence": "Exposed samples have been analysed for four DT plasma discharges at plasma currents of 1.0 and 1.8 MA.",
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"category": "Nuclear Fusion Device Type",
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"sentence": "The results at 1.0 MA are in good agreement with predictions for first orbit alpha loss at 3.5 MeV.",
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"sentence": "The 1.8 MA results, however, indicate a large anomalous loss of partially thermalized alphas at an energy 30 below the birth energy and at a total fluence nearly an order of magnitude above the expected first orbit loss.",
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"sentence": "This anomalous loss is not observed with the lost alpha scintillator detectors in DT plasmas but does resemble the anomalous delayed loss seen in DD plasmas.",
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"abstract": "During 1997, JET carried out a campaign of operation in deuteriumtritium. A total of 99 grams of tritium was admitted to the torus using gas puffing and neutral beam injection. With a site invento...",
"title": "Results of Recent Deuterium/Tritium Experiments in JET",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST98-A11963633",
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"Jet (fluid)",
"Magnetic confinement fusion",
"Nuclear physics",
"Materials science",
"Neutral beam injection",
"Plasma confinement",
"Iter tokamak",
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"abstract": "The properties of the weakly bound SL 0-state in the ion are investigated with the use of the results of highly accurate computations. The hyperfine structure splitting of this ion is investigated. We also evaluate the lifetime of the ion against the nuclear , -fusion and discuss a possibility of evaluating the corresponding annihilation rates.",
"title": "On the bound state of the antiproton-deuterium-tritium ion",
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"abstract": "Physical properties of tritium T and deuterium D have been of great interest as a fuel for nuclear fusion. However, several kinds of the physical properties in a cryogenic environment have not been reported. Optical properties in liquid and solid phases are indispensable for the quality control of the DT fuel. We study the dependence of the refractive index of solid DT on temperature. A dedicated cryogenic system has been developed and forms a transparent solid DT in a prism cell. Refractive index measurements based on Snells law were conducted. The refractive indexes of solid DT are from 1.1618 0.0002 to 1.1628 0.0002 in the temperature range of 19.40 K to 17.89 K.",
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"abstract": "The confinement and heating of supershot plasmas are significantly enhanced with tritium beam injection relative to deuterium injection in the Tokamak Fusion Test Reactor. The global energy confinement and local thermal transport are analyzed for deuterium and tritium fueled plasmas to quantify their dependence on the average mass of the hydrogenic ions. Radial profiles of the deuterium and tritium densities are determined from the DT fusion neutron emission profile. The inferred scalings with average isotopic mass are quite strong, with τEA0.850.20, τEthermalA0.890.20, χitotA2.60.5, and DeA1.40.2 at fixed Pinj. For fixed local plasma parameters χitotA1.80.4 is obtained. The quoted 2σ uncertainties include contributions from both diagnostic errors and shot irreproducibility, and are conservatively constructed to attribute the entire scatter in the regressed parameters to uncertainties in the exponent on plasma mass.",
"title": "Isotopic scaling of confinement in deuterium–tritium plasmas",
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"Atomic physics",
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"Plasma parameters",
"Tokamak Fusion Test Reactor",
"Plasma diagnostics",
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"abstract": "Both global and thermal energy confinement improve in high-temperature supershot plasmas in the Tokamak Fusion Test Reactor TFTR when deuterium beam heating is partially or wholly replaced by tritium beam heating. For the same heating power, the tritium-rich plasmas obtain up to 22 higher total energy, 30 higher thermal ion energy, and 20-25 higher central ion temperature. Kinetic analysis of the temperature and density profiles indicates a favorable isotopic scaling of ion heat transport and electron particle transport, with τEia2 A0.7-0.8 and τpea A0.8.",
"title": "Isotopic scaling of transport in deuterium-tritium plasmas",
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"Electron",
"Atomic physics",
"Materials science",
"Tokamak Fusion Test Reactor",
"Deuterium",
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"abstract": "Consistent descriptions of the equation of states and information about the transport coefficients of the deuterium-tritium mixture are demonstrated through quantum molecular dynamic QMD simulations up to a density of 600 gcm and a temperature of eV. Diffusion coefficients and viscosity are compared to the one-component plasma model in different regimes from the strong coupled to the kinetic one. Electronic and radiative transport coefficients, which are compared to models currently used in hydrodynamic simulations of inertial confinement fusion, are evaluated up to 800 eV. The Lorentz number is discussed from the highly degenerate to the intermediate region. One-dimensional hydrodynamic simulation results indicate that different temperature and density distributions are observed during the target implosion process by using the Spitzer model and ab initio transport coefficients.",
"title": "Transport properties of dense deuterium-tritium plasmas",
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"abstract": "The covariant equation for the three-body deuterium system is discussed, and reduced to a three-dimensional equation for the case of instantaneous two-body interactions. A noncovariant perturbation scheme, based on this three-dimensional equation, was employed to calculate the hyperfine structure hfs to order hfs for. The results are compared with the experimental values, and shown to be compatible. Final determination of the theoretical values and the adequacy of the theory is shown to depend critically on the determination of a number of experimental quantities, in particular on a more precise measurement of, of the nucleon electric and magnetic form factors and associated nucleon polarization, of the presence and magnitude of a two-nucleon spin-orbit potential, and of the singlet effective range.",
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"abstract": "An overview of JET experimental results in DT plasmas directly relevant to ITER modes of operation is presented. Experiments in DT mixtures varying from 1000 to 1090 and those carried out in hydrogen plasmas show that the H mode threshold power has an approximately inverse isotope mass dependence. Matching some of the key dimensionless parameters to the ITER values, the ITER similarity experiments with ITER shape and safety factor show that the global energy confinement time is practically independent of isotopic mass A0.030.08, where A is the atomic mass of the hydrogenic species. Subtracting the edge pedestal energy which scales as A0.570.2 from the total stored energy leads to a A-0.170.1 dependence of confinement in the plasma core, very similar to that expected from the gyro-Bohm transport A-0.2 model. The observed scaling of the edge pedestal energy is consistent with a model in which the edge pressure gradient saturates at the ballooning limit over a region of width that scales as the ion poloidal Larmor radius governed by the average energy of the fast ions in the edge. The steady state total stored energy for a given input power in both ICRH and NBI discharges is the same despite the lower edge pedestal in the ICRH case, which is compensated for by more peaked power deposition profiles in ICRH. The ELM frequency is smaller with NBI it decreases with isotopic mass in both NBI and ICRH discharges. A steady state, type I ELMy H mode discharge with ITER shape and at 3.8 T3.8 MA with an input power of 22 MW produced a Q 0.18 for 3.5 and extrapolates well to ignition with ITER parameters. Here, Q is the ratio of fusion output power to input power. The thermal ELMy H mode confinement in both deuterium and tritium gas fuelled plasmas decreases significantly when the plasma density exceeds 0.75 of the Greenwald nGW limit, and the maximum density achieved is 0.85nGW. In L mode, the density limit decreases with increasing isotope mass roughly in accordance with code predictions. ITER reference ICRH scenarios have been evaluated. Second harmonic heating of tritium at the densities available in JET produces strong tails and heats electrons predominantly as expected. The 3He minority in 5050 DT and tritium dominated plasmas showed strong bulk ion heating leading to ion temperatures up to 13 keV with ICRH alone. Deuterium minority ion cyclotron heating in tritium plasmas at a power level of 6 MW produced steady state record values of Q 0.22 for more than 2.5 .",
"title": "Overview of ITER physics deuterium-tritium experiments in JET",
"URL": "https://ui.adsabs.harvard.edu/abs/1999NucFu..39..235J/abstract",
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"Physics",
"Ion",
"Atomic mass",
"Atomic physics",
"Nuclear physics",
"Dimensionless quantity",
"Cyclotron",
"Deuterium",
"Plasma",
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"Tritium illumination"
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"year_published": 1999,
"first_author": "J. Jacquinot",
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"abstract": "Recent scientific and technical progress in magnetic fusion experiments has resulted in the achievement of plasma parameters density and temperature which made possible the production of significant bursts of fusion power from deuterium-tritium fuels and the first studies of the physics of burning plasmas. The key scientific issues in studying the reacting plasma core are plasma confinement, magnetohydrodynamic MHD stability, and the confinement and loss of energetic fusion products from the reacting fuel ions. Progress in the development of regimes of operation that both have good confinement and are MHD stable has made possible a broad study of problems in burning-plasma physics. The technical and scientific results from deuterium-tritium experiments on the Joint European Torus JET and the Tokamak Fusion Test Reactor TFTR are reviewed, with particular emphasis on alpha-particle physics issues.",
"title": "Results from deuterium-tritium tokamak confinement experiments",
"URL": "http://www.osti.gov/scitech/servlets/purl/304206",
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"Physics",
"Magnetic confinement fusion",
"Nuclear physics",
"Fusion power",
"Joint European Torus",
"Tokamak Fusion Test Reactor",
"Magnetohydrodynamics",
"Plasma diagnostics",
"Plasma"
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"year_published": 1998,
"first_author": "R. J. Hawryluk",
"scholarly_citations_count": 113,
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"abstract": "Rates of neutron production in deuterium-tritium D-T plasmas below the temperature of 100 keV have been widely studied with analytical cross sections based on nuclear physics. In the present work...",
"title": "A Numerical Algorithm for Nuclear Reaction in Deuterium-Tritium Plasma",
"URL": "https://ans.org/pubs/journals/fst/a_45272",
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"Work (thermodynamics)",
"Neutron",
"Neutron source",
"Nuclear physics",
"Materials science",
"Nuclear reaction",
"Deuterium",
"Tritium",
"Plasma"
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"year_published": 2019,
"first_author": "Dongmei Pan",
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"abstract": "The thermonuclear burn characteristics of compressed deuterium-tritium microspheres are simulated with LARED-S code based on the isochoric and isobaric models. Two examples of the isochoric model are simulated and compared with the other present data for validating the LARED-S code. For the isobaric model, numerical results characterizing the thermonuclear burn for a broad range of initial conditions are presenteal. It is shown that the yield and burn-up fraction increase with the total fuel mass, pressure and main-fuel density. It is necessary for the hot-spot to reach temperatures up to 70 to 80 MK and areal density 3 to 4 kg -2 to obtain considerable fusion energy. If the main-fuel density is increased high enough, the hot-spot condition for ignition could be broadened to a lower limit. Finally, the results of the isobaric model are compared with those of the actual ignition targets simulated with the LARED-S code.",
"title": "Thermonuclear burn characteristics of compressed deuterium-tritium microspheres",
"URL": "http://wulixb.iphy.ac.cn/en/article/doi/10.7498/aps.59.2381?viewType=HTML",
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"abstract": "A fusion ignition experiment will produce large numbers of neutrons and alpha particles. The detection and characterization of these particles will be important in understanding the physics of igni...",
"title": "Diagnostic System for the Deuterium-Tritium Phase of the IGNITEX Experiment",
"URL": "https://www.ans.org/pubs/journals/fst/a_29626",
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"abstract": "One of the goals of 21st-century physicscontrolling the implosion of a target and initiating nuclear fusionhas its origins in one of the puzzles of 19th-century physics. The understanding of thermal radiation emitted from a cavity blackbody radiation, which is an important component of the fusion problem, began by abandoning classical physics and adopting the revolutionary idea of energy quantization. Thermal radiation has reappeared in the fusion problem because the powerful megajoule-class lasers do not implode their targets directlyinstead, they create intense radiation pressure within a cavity. On pages 1231 and 1228 of this issue, Li et al. 1 and Glenzer et al. 2 show that the distribution of radiation inside a cavity can be accurately controlled to create a symmetrical implosion, thereby removing major obstacles to the realization of fusion energy in the laboratory. These new insights promise another revolution in physics in the near future, one that provides access to new states of matter with unprecedented energy densities.",
"title": "Controlling Implosion Symmetry Around a Deuterium-Tritium Target",
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"sentence": "Thermal radiation has reappeared in the fusion problem because the powerful megajoule-class lasers do not implode their targets directlyinstead, they create intense radiation pressure within a cavity.",
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"sentence": "On pages 1231 and 1228 of this issue, Li et al. 1 and Glenzer et al. 2 show that the distribution of radiation inside a cavity can be accurately controlled to create a symmetrical implosion, thereby removing major obstacles to the realization of fusion energy in the laboratory.",
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"abstract": "This paper describes results of the first experiments utilizing high-power ion cyclotron range of frequency ICRF to heat deuterium-tritium D-T plasmas in reactor-relevant regimes on the Tokamak Fusion Test Reactor TFTR. Results from these experiments have demonstrated efficient core, second harmonic, tritium heating of D-T supershot plasmas with tritium concentrations ranging from 6--40. Significant direct ion heating on the order of 60 of the input radio frequency rf power has been observed. The measured deposition profiles are in good agreement with two-dimensional modeling code predictions. Confinement in an rf-heated supershot is at least similar to that without rf, and possibly better in the electron channel. Efficient electron heating via mode conversion of fast waves to ion Bernstein waves IBW has been demonstrated in ohmic, deuterium-deuterium and DT-neutral beam injection plasmas with high concentrations of minority He nHen 10. By changing the He concentration or the toroidal field strength, the location of the mode-conversion radius was varied. The power deposition profile measured with rf power modulation showed that up to 70 of the power can be deposited on electrons at an off-axis position. Preliminary results with up to 4 MW coupled into the plasma by 90-degree phased antennas showed directional propagation of the mode-converted IBW. Heat wave propagation showed no strong inward thermal pinch in off-axis heating of an ohmically-heated OH target plasma in TFIR.",
"title": "ICRF heating and transport of deuterium-tritium plasmas in TFTR",
"URL": "http://www.osti.gov/scitech/servlets/purl/10115936",
"fields_of_study": [
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"Ion",
"Atomic physics",
"Materials science",
"Electron temperature",
"Tokamak Fusion Test Reactor",
"Helium-3",
"Cyclotron",
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"sentence": "The power deposition profile measured with rf power modulation showed that up to 70 of the power can be deposited on electrons at an off-axis position.",
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{
"abstract": "Thermalization of hot tensuremath atoms formed in-DT- mixtures and relaxation of the triplet hyperfine state of tensuremath are treated by Monte Carlo simulation. The cross sections for collisions with molecular targets are derived from cross sections for collisions with the component atoms. The statistical histograms for the time-dependent velocity distributions are fitted by sums of two Maxwellian functions, and the coefficients and temperatures are tabulated for tritium fractions of 10, 50, and 90 and mixture temperatures of 30, 100, and 300 K. The results provide a basis for analyzing some previously puzzling aspects of the observed cycling rate in recent muon-catalyzed-fusion experiments. In particular, thermalization is found to be very incomplete for some low-temperature targets. Also, the relative rates of kinetic thermalization and hyperfine-state relaxation depend strongly on the target tritium fraction, and hyperfine effects may be observable. The velocity distribution of tensuremath atoms at times of molecular dtensuremath formation is shown to depend only rather weakly on the initial velocity distribution, which is not well known.",
"title": "Thermalization of the muonic tritium atom in deuterium-tritium mixtures.",
"URL": "https://europepmc.org/article/MED/9897587",
"fields_of_study": [
"Physics",
"Hyperfine structure",
"Kinetic energy",
"Thermalisation",
"Atom",
"Atomic physics",
"Monte Carlo method",
"Relaxation (physics)",
"Deuterium",
"Tritium"
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"year_published": 1986,
"first_author": "James S. Cohen",
"scholarly_citations_count": 26,
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"sentence": "In particular, thermalization is found to be very incomplete for some low-temperature targets.",
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"abstract": "Abstract The controlling parameters regarding tritium burn efficiency TBE are derived from first principles and shown to depend fundamentally on the permitted He gas fraction in the divertor and effective pumping speeds of He ash and unburned hydrogenic fuel. The analysis is generic to any equilibrated magnet fusion plasma using a divertor for particle exhaust. The He gas fraction in the plasma limits the maximum TBE due to the link between ash dilution effects in the core plasma and fusion performance. High TBE in magnetic fusion devices is counter-correlated to achieving high gain and power density for commercial fusion. The impact of TBE on fusion performance for several figures of merit are derived, including power density, required τ product, and plasma energy gain Q . The TBE formulation presented here is applied to existing devices, based on published data of enrichment and τ He from research tokamaks. This assessment strongly motivates exploration of technologies that would enhance the effective pumping speed of He to fuel out of the plasma.",
"title": "Tritium burn efficiency in deuterium–tritium magnetic fusion",
"URL": "https://iopscience.iop.org/article/10.1088/1741-4326/acf3fb/pdf",
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"Divertor",
"Materials science",
"Algorithm",
"Physics",
"Plasma",
"Computer science",
"Nuclear physics",
"Tokamak"
],
"year_published": 2023,
"first_author": "D.G. Whyte",
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},
{
"abstract": "The kinetic characteristics of muon-catalyzed deuterium-tritium D-T fission processes are considered. Rate equations for the dominant muonic and nonmuonic reactions are formulated and the associated particle densities determined as a function of time. Parametric expressions intended to provide an indication of the energetic viability of muon-aided fusion reactions are formulated and evaluated. It appears that muon-catalyzed D-T fusion at low temperature does possess the potential of energy gain under certain experimental conditions. 12 refs.",
"title": "Kinetics and Energetics of Muon-Catalyzed Deuterium-Tritium Fusion",
"URL": "http://www.osti.gov/scitech/biblio/6825696",
"fields_of_study": [
"Fission",
"Kinetic energy",
"Fusion",
"Nuclear physics",
"Materials science",
"Muon",
"Nuclear reaction",
"Deuterium",
"Tritium",
"Nuclear fusion"
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"year_published": 1982,
"first_author": "S. G. Lie",
"scholarly_citations_count": 10,
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{
"abstract": "The collisional transport theory for a multispecies Tokamak plasma is applied to discuss the properties of a deuterium-tritium mixture. It is shown that in the Pfirsch-Schluter regime tritium and deuterium tend to separate, tritium accumulating in the colder regions. This effect, which is small in the other transport regimes, is not appreciably affected by the presence of a reasonable amount of impurities.",
"title": "Neoclassical transport properties of a deuterium-tritium Tokamak plasma",
"URL": "https://iopscience.iop.org/article/10.1088/0741-3335/26/1B/002/pdf",
"fields_of_study": [
"Tokamak",
"Nuclear physics",
"Materials science",
"Transport theory",
"Deuterium",
"Tritium",
"Impurity",
"Plasma"
],
"year_published": 1984,
"first_author": "A. Nocentini",
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"abstract": "The phenomenology of optimized laserdriven DT sphere implosions leading to efficient thermonuclear burn is reviewed. The optimal laser deposition profile for spheres is heuristically derived. The performance of a 7.5 μg sphere, exposed to its optimal 5.3 kJ pulse, is scrutinized in detail. The timing requirements for efficient central ignition of propagating burn in the sphere are carefully explored. The difficulties stemming from superthermal electron production and thermal flux limitation are discussed. The hydroburn performance of spheres is characterized as a function of the pulse energy, peak power, time scale, pulse exponent, wavelength, and on the degree of flux limitation. The optimal pulse parameters are determined for spheres with masses ranging from 40 ng to 250 μg, requiring from 50 J to 150 kJ of input energy, and the corresponding optimal performance levels are calculated. Discussion is given to the hydroburn performance of new structured fusion targets, in which the DT is contained as a gas or frozen as an ice shell inside a high Z pushertamper layer.",
"title": "Hydrodynamics and burn of optimally imploded deuterium‐tritium spheres",
"URL": "http://scitation.aip.org/content/aip/journal/pof1/18/7/10.1063/1.861244",
"fields_of_study": [
"Physics",
"Electron",
"Ignition system",
"Heat flux",
"Atomic physics",
"Laser",
"Deuterium",
"Wavelength",
"Thermonuclear fusion",
"SPHERES"
],
"year_published": 1975,
"first_author": "R. J. Mason",
"scholarly_citations_count": 38,
"NER-RE": [
{
"sentence": "The phenomenology of optimized laserdriven DT sphere implosions leading to efficient thermonuclear burn is reviewed.",
"entities": [
{
"category": "Nuclear Fusion Technique",
"entity": "laser-driven"
},
{
"category": "Nuclear Fusion System Component",
"entity": "DT sphere"
},
{
"category": "Physical Process",
"entity": "implosions"
},
{
"category": "Physical Process",
"entity": "thermonuclear burn"
},
{
"category": "Plasma property",
"entity": "thermonuclear burn"
},
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"category": "Concept",
"entity": "phenomenology"
}
]
},
{
"sentence": "The optimal laser deposition profile for spheres is heuristically derived.",
"entities": [
{
"category": "Nuclear Fusion Technique",
"entity": "laser deposition"
}
]
},
{
"sentence": "The performance of a 7.5 μg sphere, exposed to its optimal 5.3 kJ pulse, is scrutinized in detail.",
"entities": [
{
"category": "Nuclear Fusion System Component",
"entity": "sphere"
},
{
"category": "Experimental Apparatus",
"entity": "pulse"
}
]
},
{
"sentence": "The timing requirements for efficient central ignition of propagating burn in the sphere are carefully explored.",
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{
"category": "Concept",
"entity": "central ignition"
},
{
"category": "Concept",
"entity": "propagating burn"
},
{
"category": "Plasma property",
"entity": "efficient ignition"
},
{
"category": "Nuclear Fusion System Configuration",
"entity": "sphere"
}
]
},
{
"sentence": "The difficulties stemming from superthermal electron production and thermal flux limitation are discussed.",
"entities": [
{
"category": "Physical Process",
"entity": "thermal flux limitation"
},
{
"category": "Particle",
"entity": "electron"
},
{
"category": "Plasma property",
"entity": "superthermal electron production"
}
]
},
{
"sentence": "The hydroburn performance of spheres is characterized as a function of the pulse energy, peak power, time scale, pulse exponent, wavelength, and on the degree of flux limitation.",
"entities": [
{
"category": "Physics Entity",
"entity": "pulse energy"
},
{
"category": "Physics Entity",
"entity": "peak power"
},
{
"category": "Physics Entity",
"entity": "time scale"
},
{
"category": "Physics Entity",
"entity": "pulse exponent"
},
{
"category": "Physics Entity",
"entity": "wavelength"
},
{
"category": "Physics Entity",
"entity": "flux limitation"
},
{
"category": "Physical Process",
"entity": "hydroburn performance"
}
]
},
{
"sentence": "The optimal pulse parameters are determined for spheres with masses ranging from 40 ng to 250 μg, requiring from 50 J to 150 kJ of input energy, and the corresponding optimal performance levels are calculated.",
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{
"category": "Physics Entity",
"entity": "pulse parameters"
},
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"category": "Physics Entity",
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"category": "Physics Entity",
"entity": "input energy"
},
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"entity": "performance levels"
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{
"sentence": "Discussion is given to the hydroburn performance of new structured fusion targets, in which the DT is contained as a gas or frozen as an ice shell inside a high Z pushertamper layer.",
"entities": [
{
"category": "Nuclear Fusion System Component",
"entity": "pusher-tamper layer"
},
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"category": "Chemical Element or Compound",
"entity": "DT"
},
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"category": "Nuclear Fusion System Configuration",
"entity": "structured fusion targets"
},
{
"category": "Nuclear Fusion System Component",
"entity": "ice shell"
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{
"category": "Nuclear Fusion Technique",
"entity": "hydroburn"
}
]
}
]
},
{
"abstract": "All major JET systems have been fully commissioned for D-T and the DTE1 series of experiments has started with the D-T fuel mixture and operating conditions foreseen for ITER. In the area of ITER physics, significant results have been produced in both D-D and D-T. In D-D, the LH threshold power database has been extended, the bounds on edge-electron temperature and density in ELMy H-modes have been defined and the advantages of Types I and III ELMy discharges have been compared. In D-T plasmas, the isotope effect on H-mode threshold power and transport has been determined so that a more accurate assessment can be made of the ignition margin and heating requirements for ITER. Trace tritium experiments have provided first particle transport measurements and an assessment of the ITER reference ion-cyclotron resonance-frequency heating scenarios has been started, In the area of fusion performance, record D-D neutron yields have been obtained by controlling the plasma and current profiles in hot ion ELM-free H-modes and optimized shear modes. In D-T, internal transport barriers have been readily established in optimized shear discharges and Alfven eigenmodes have been observed.",
"title": "Latest JET results in deuterium and deuterium-tritium plasmas",
"URL": "https://infoscience.epfl.ch/record/119584",
"fields_of_study": [
"Jet (fluid)",
"Ion",
"Neutron",
"Ignition system",
"Nuclear physics",
"Materials science",
"Deuterium",
"Tritium",
"Shear (sheet metal)",
"Plasma"
],
"year_published": 1997,
"first_author": "J. M. Adams",
"scholarly_citations_count": 43,
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"sentence": "All major JET systems have been fully commissioned for D-T and the DTE1 series of experiments has started with the D-T fuel mixture and operating conditions foreseen for ITER.",
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"category": "Nuclear Fusion Experimental Facility",
"entity": "JET"
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"category": "Experimental Apparatus",
"entity": "DTE1"
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"category": "Nuclear Fusion System Configuration",
"entity": "D-T fuel mixture"
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"entity": "D-T"
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"category": "Nuclear Fusion Experimental Facility",
"entity": "ITER"
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]
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"sentence": "In the area of ITER physics, significant results have been produced in both D-D and D-T. In D-D, the LH threshold power database has been extended, the bounds on edge-electron temperature and density in ELMy H-modes have been defined and the advantages of Types I and III ELMy discharges have been compared.",
"entities": [
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"category": "Plasma property",
"entity": "H-mode"
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"entity": "ELMy"
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{
"category": "Plasma property",
"entity": "edge-electron temperature"
},
{
"category": "Plasma property",
"entity": "edge-electron density"
},
{
"category": "Nuclear Fusion Technique",
"entity": "D-D"
},
{
"category": "Nuclear Fusion Technique",
"entity": "D-T"
},
{
"category": "Database",
"entity": "LH threshold power database"
},
{
"category": "Research field",
"entity": "ITER physics"
}
]
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{
"sentence": "In D-T plasmas, the isotope effect on H-mode threshold power and transport has been determined so that a more accurate assessment can be made of the ignition margin and heating requirements for ITER.",
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{
"category": "Nuclear Fusion Experimental Facility",
"entity": "ITER"
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"category": "Plasma property",
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"category": "Plasma dynamic and behavior",
"entity": "plasma transport"
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{
"category": "Plasma dynamic and behavior",
"entity": "transport"
}
]
},
{
"sentence": "Trace tritium experiments have provided first particle transport measurements and an assessment of the ITER reference ion-cyclotron resonance-frequency heating scenarios has been started, In the area of fusion performance, record D-D neutron yields have been obtained by controlling the plasma and current profiles in hot ion ELM-free H-modes and optimized shear modes.",
"entities": [
{
"category": "Particle",
"entity": "tritium"
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"category": "Plasma property",
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"category": "Plasma property",
"entity": "edge-localized modes (ELMs)"
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"category": "Plasma property",
"entity": "optimized shear modes"
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"category": "Plasma dynamic and behavior",
"entity": "plasma transport"
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"category": "Detection and Monitoring Systems",
"entity": "D-D neutron yields"
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"category": "Nuclear Fusion Experimental Facility",
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]
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{
"sentence": "In D-T, internal transport barriers have been readily established in optimized shear discharges and Alfven eigenmodes have been observed.",
"entities": [
{
"category": "Plasma dynamic and behavior",
"entity": "internal transport barriers"
},
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"category": "Plasma dynamic and behavior",
"entity": "Alfven eigenmodes"
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"category": "Nuclear Fusion System Configuration",
"entity": "optimized shear discharges"
}
]
}
]
},
{
"abstract": "The deuterium-tritium D-T experimental program on the Tokamak Fusion Test Reactor TFTR is underway and routine tritium operations have been established. The technology upgrades made to the TFTR facility have been demonstrated to be sufficient for supporting both operations and maintenance for an extended D-T campaign. To date fusion power has been increased to 9 MW and several physics results of importance to the D-T reactor regime have been obtained electron temperature, ion temperature, and plasma stored energy all increase substantially in the D-T regime relative to the D-D regime at the same neutral beam power and comparable limiter conditioning possible alpha electron heating is indicated and energy confinement improvement with average ion mass is observed and alpha particle losses appear to be classical with no evidence of TAE mode activity up to the P 6 MW level. Instability in the TAE mode frequency range has been observed at P 7 MW and its effect on performance is under investigation. Preparations are underway to enhance the alpha particle density further by increasing fusion power and by extending the neutral beam pulse length to permit alpha particle effects of relevance to the ITER regime to be more fullymore explored. less",
"title": "Deuterium-Tritium Experiments on the Tokamak Fusion Test Reactor",
"URL": "https://ans.org/pubs/journals/fst/a_40191",
"fields_of_study": [
"Nuclear physics",
"Materials science",
"Electron temperature",
"Fusion power",
"Tokamak Fusion Test Reactor",
"Range (particle radiation)",
"Limiter",
"Deuterium",
"Alpha particle",
"Plasma"
],
"year_published": 1994,
"first_author": "J. Hosea",
"scholarly_citations_count": 11,
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"category": "Chemical Element or Compound",
"entity": "Deuterium"
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"category": "Chemical Element or Compound",
"entity": "Tritium"
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"category": "Chemical Element or Compound",
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]
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"sentence": "The technology upgrades made to the TFTR facility have been demonstrated to be sufficient for supporting both operations and maintenance for an extended D-T campaign.",
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"sentence": "To date fusion power has been increased to 9 MW and several physics results of importance to the D-T reactor regime have been obtained electron temperature, ion temperature, and plasma stored energy all increase substantially in the D-T regime relative to the D-D regime at the same neutral beam power and comparable limiter conditioning possible alpha electron heating is indicated and energy confinement improvement with average ion mass is observed and alpha particle losses appear to be classical with no evidence of TAE mode activity up to the P 6 MW level.",
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{
"category": "Nuclear Fusion Experimental Facility",
"entity": "D-T reactor"
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"category": "Nuclear Fusion Technique",
"entity": "magnetic confinement"
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"category": "Nuclear Fusion Device Type",
"entity": "Tokamak"
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"category": "Nuclear Fusion System Component",
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"category": "Experimental Apparatus",
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"category": "Physical Process",
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"category": "Physics Entity",
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},
{
"category": "Physics Entity",
"entity": "ion temperature"
},
{
"category": "Physics Entity",
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"category": "Field Configuration",
"entity": "magnetic field"
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{
"category": "Particle",
"entity": "alpha particle"
},
{
"category": "Chemical Element or Compound",
"entity": "deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "tritium"
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"category": "Plasma property",
"entity": "plasma temperature"
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"category": "Plasma property",
"entity": "plasma density"
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"category": "Plasma event",
"entity": "TAE mode activity"
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"category": "Plasma dynamic and behavior",
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{
"category": "Detection and Monitoring Systems",
"entity": "plasma diagnostics"
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"category": "Theory and Calculation",
"entity": "energy confinement"
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"sentence": "Instability in the TAE mode frequency range has been observed at P 7 MW and its effect on performance is under investigation.",
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{
"category": "Plasma property",
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"category": "Plasma dynamic and behavior",
"entity": "Instability"
}
]
},
{
"sentence": "Preparations are underway to enhance the alpha particle density further by increasing fusion power and by extending the neutral beam pulse length to permit alpha particle effects of relevance to the ITER regime to be more fullymore explored.",
"entities": [
{
"category": "Particle",
"entity": "alpha particle"
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"category": "Nuclear Fusion Experimental Facility",
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"entity": "fusion power"
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"category": "Experimental Apparatus",
"entity": "neutral beam"
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{
"abstract": "The effects of nonequilibrium particle distributions resulting from rapid deuterium-tritium burning in plasmas are investigated using a FokkerPlanck code that incorporates small-angle Coulomb scattering, bremsstrahlung, Compton scattering, and light-ion fusion. For inertial confinement fusion environments, it is found that deviations away from Maxwellian distributions for either deuterium or tritium ions are small and result in 1 changes in the energy production rates. The deuterium and tritium effective temperatures are not equal, but differ by only about 2.5 near the time of peak burn rate. Simulations with high Z Xe dopants show that the dopant temperature closely tracks that of the fuel. On the other hand, fusion product ion distributions are highly non-Maxwellian, and careful treatments of energy-exchange between these ions and other particles is important for determining burn rates.",
"title": "Effects of nonequilibrium particle distributions in deuterium-tritium burning",
"URL": "http://ui.adsabs.harvard.edu/abs/2010PhPl...17a2707M/abstract",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Ion",
"Atomic physics",
"Scattering",
"Elastic scattering",
"Charged particle",
"Deuterium",
"Burn rate",
"Compton scattering"
],
"year_published": 2010,
"first_author": "David Michta",
"scholarly_citations_count": 13,
"NER-RE": [
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"sentence": "The effects of nonequilibrium particle distributions resulting from rapid deuterium-tritium burning in plasmas are investigated using a FokkerPlanck code that incorporates small-angle Coulomb scattering, bremsstrahlung, Compton scattering, and light-ion fusion.",
"entities": [
{
"category": "Particle",
"entity": "deuterium"
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"category": "Particle",
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"category": "Physical Process",
"entity": "light-ion"
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"category": "Physical Process",
"entity": "Coulomb scattering"
},
{
"category": "Physical Process",
"entity": "bremsstrahlung"
},
{
"category": "Physical Process",
"entity": "Compton scattering"
},
{
"category": "Physical Process",
"entity": "fusion"
},
{
"category": "Software and simulation",
"entity": "FokkerPlanck code"
},
{
"category": "Plasma property",
"entity": "nonequilibrium particle distributions"
}
]
},
{
"sentence": "For inertial confinement fusion environments, it is found that deviations away from Maxwellian distributions for either deuterium or tritium ions are small and result in 1 changes in the energy production rates.",
"entities": [
{
"category": "Nuclear Fusion Technique",
"entity": "inertial confinement fusion"
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{
"category": "Chemical Element or Compound",
"entity": "deuterium"
},
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"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Particle",
"entity": "ions"
},
{
"category": "Physics Entity",
"entity": "energy production rates"
},
{
"category": "Concept",
"entity": "Maxwellian distributions"
}
]
},
{
"sentence": "The deuterium and tritium effective temperatures are not equal, but differ by only about 2.5 near the time of peak burn rate.",
"entities": [
{
"category": "Particle",
"entity": "deuterium"
},
{
"category": "Particle",
"entity": "tritium"
},
{
"category": "Plasma property",
"entity": "effective temperatures"
},
{
"category": "Plasma event",
"entity": "peak burn rate"
},
{
"category": "Time reference",
"entity": "time of peak burn rate"
}
]
},
{
"sentence": "Simulations with high Z Xe dopants show that the dopant temperature closely tracks that of the fuel.",
"entities": [
{
"category": "Chemical Element or Compound",
"entity": "Xe"
},
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"category": "Plasma property",
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{
"category": "Software and simulation",
"entity": "Simulations"
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{
"category": "Physics Entity",
"entity": "fuel temperature"
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"entity": "fuel"
}
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{
"sentence": "On the other hand, fusion product ion distributions are highly non-Maxwellian, and careful treatments of energy-exchange between these ions and other particles is important for determining burn rates.",
"entities": [
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"category": "Concept",
"entity": "Maxwellian"
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"category": "Physical Process",
"entity": "energy-exchange"
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{
"category": "Particle",
"entity": "ions"
},
{
"category": "Plasma property",
"entity": "fusion product ion distributions"
},
{
"category": "Plasma property",
"entity": "burn rates"
}
]
}
]
},
{
"abstract": "The phenomenology of thermonuclear burn in deuteriumtritium microspheres at high densities is described, and numerical results characterizing the burn for a broad range of initial conditions are given. The fractional burnup, bootstrapheating, and depletion of the DT fuel, its expansive disassembly, and thermonuclear ignition by propagating burn from central hot spots in the microspheres are discussed. Extensive numerical results from a 3 T Lagrangian simulation code are presented. The yields Y0 from uniform 10, 1, and 0.1 μg microspheres with densities ρ 1 to 4 104 gcm3 and temperatures Te Ti 1.8 to 100 keV are given. It is shown that Y0 ρR, ρR 0.3 R is the microsphere radius or, equivalently, Y0 ρ23 for spheres of fixed mass . The gainfactor G0 Y0mI0 I0 is the internal energy is shown to measure burn efficiency in uniform microspheres. More than a fourfold increment in the gain factor is shown to derive from apportionment of the internal energy in a central hot spot. The limit...",
"title": "Thermonuclear burn characteristics of compressed deuterium‐tritium microspheres",
"URL": "https://www.osti.gov/servlets/purl/4429729/",
"fields_of_study": [
"Physics",
"Neutron",
"Ignition system",
"Atomic physics",
"Burnup",
"Range (particle radiation)",
"Deuterium",
"Internal energy",
"Thermonuclear fusion",
"Radius"
],
"year_published": 1974,
"first_author": "G. S. Fraley",
"scholarly_citations_count": 260,
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"entity": "thermonuclear burn"
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"category": "Nuclear Fusion System Component",
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"sentence": "The fractional burnup, bootstrapheating, and depletion of the DT fuel, its expansive disassembly, and thermonuclear ignition by propagating burn from central hot spots in the microspheres are discussed.",
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"entity": "microspheres"
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{
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"entity": "DT fuel"
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"entity": "expansive disassembly"
},
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"category": "Physical Process",
"entity": "depletion"
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"entity": "bootstrap heating"
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]
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{
"abstract": "This paper describes results of the first experiments utilizing high-power ion cyclotron range of frequency ICRF to heat deuterium-tritium D-T plasmas in reactor-relevant regimes on the Tokamak Fusion Test Reactor TFTR. Results from these experiments have demonstrated efficient core, second harmonic, tritium heating of D-T supershot plasmas with tritium concentrations ranging from 6-40. Significant direct ion heating on the order of 60 of the input radio frequency rf power has been observed. The measured deposition profiles are in good agreement with two-dimensional modeling code predictions. Energy confinement in an rf-heated supershot is at least similar to that without rf, and possibly better in the electron channel. Efficient electron heating via mode conversion of fast waves to ion Bernstein waves IBW has been demonstrated in ohmic, deuterium-deuterium and DT-neutral beam injection plasmas with high concentrations of minority 3He n3Hene 15- 30. By changing the 3He concentration or the toroidal field strength, the location of the mode-conversion radius was varied. The power deposition profile measured with rf power modulation indicated that up to 70 of the power can be deposited on electrons at an off-axis position. Preliminary results with up to 4 MW coupled into the plasma by 90-degree phased antennas showed directional propagation of the mode-converted IBW. Analysis of heat wave propagation showed no strong inward thermal pinch in off-axis heating of an ohmically-heated target plasma in TFTR.",
"title": "ICRF Heating and Transport of Deuterium-Tritium Plasmas in TFTR",
"URL": "https://digital.library.unt.edu/ark:/67531/metadc618424/m2/1/high_res_d/113956.pdf",
"fields_of_study": [
"Tokamak Fusion Test Reactor",
"Plasma",
"Atomic physics",
"Materials science",
"Tokamak",
"Cyclotron",
"Dielectric heating",
"Joule heating",
"Deuterium",
"RF power amplifier",
"Fusion power",
"Neutral beam injection",
"Electron",
"Nuclear physics",
"Physics",
"Dielectric",
"Optoelectronics",
"Amplifier",
"CMOS",
"Composite material"
],
"year_published": 1995,
"first_author": "M. Murakami",
"scholarly_citations_count": "NaN",
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{
"sentence": "This paper describes results of the first experiments utilizing high-power ion cyclotron range of frequency ICRF to heat deuterium-tritium D-T plasmas in reactor-relevant regimes on the Tokamak Fusion Test Reactor TFTR.",
"entities": [
{
"category": "Nuclear Fusion Experimental Facility",
"entity": "Tokamak Fusion Test Reactor"
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"entity": "Tokamak"
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{
"category": "Nuclear Fusion Technique",
"entity": "ion cyclotron range of frequency (ICRF)"
},
{
"category": "Chemical Element or Compound",
"entity": "deuterium-tritium (D-T)"
},
{
"category": "Plasma property",
"entity": "D-T plasmas"
},
{
"category": "Plasma dynamic and behavior",
"entity": "heating"
}
]
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{
"sentence": "Results from these experiments have demonstrated efficient core, second harmonic, tritium heating of D-T supershot plasmas with tritium concentrations ranging from 6-40.",
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{
"category": "Plasma region",
"entity": "core"
},
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"category": "Physical Process",
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"category": "Plasma property",
"entity": "supershot plasmas"
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]
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{
"sentence": "Significant direct ion heating on the order of 60 of the input radio frequency rf power has been observed.",
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"category": "Physical Process",
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"category": "Physics Entity",
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"sentence": "The measured deposition profiles are in good agreement with two-dimensional modeling code predictions.",
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"entity": "two-dimensional modeling code predictions"
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"category": "Concept",
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}
]
},
{
"sentence": "Energy confinement in an rf-heated supershot is at least similar to that without rf, and possibly better in the electron channel.",
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"category": "Nuclear Fusion Technique",
"entity": "rf-heated supershot"
},
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"category": "Physical Process",
"entity": "energy confinement"
}
]
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"sentence": "Efficient electron heating via mode conversion of fast waves to ion Bernstein waves IBW has been demonstrated in ohmic, deuterium-deuterium and DT-neutral beam injection plasmas with high concentrations of minority 3He n3Hene",
"entities": [
{
"category": "Nuclear Fusion Technique",
"entity": "mode conversion of fast waves to ion Bernstein waves"
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"category": "Particle",
"entity": "electron"
},
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"category": "Particle",
"entity": "ion Bernstein waves"
},
{
"category": "Particle",
"entity": "3He"
},
{
"category": "Chemical Element or Compound",
"entity": "deuterium"
},
{
"category": "Plasma property",
"entity": "ohmic"
},
{
"category": "Nuclear Fusion Technique",
"entity": "neutral beam injection"
},
{
"category": "Plasma region",
"entity": "edge"
},
{
"category": "Plasma dynamic and behavior",
"entity": "heating"
}
]
},
{
"sentence": "15- 30.",
"entities": []
},
{
"sentence": "By changing the 3He concentration or the toroidal field strength, the location of the mode-conversion radius was varied.",
"entities": [
{
"category": "Particle",
"entity": "3He"
},
{
"category": "Field Configuration",
"entity": "toroidal field"
},
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"category": "Plasma region",
"entity": "mode-conversion radius"
}
]
},
{
"sentence": "The power deposition profile measured with rf power modulation indicated that up to 70 of the power can be deposited on electrons at an off-axis position.",
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"category": "Nuclear Fusion Technique",
"entity": "rf power modulation"
},
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"category": "Particle",
"entity": "electrons"
}
]
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{
"sentence": "Preliminary results with up to 4 MW coupled into the plasma by 90-degree phased antennas showed directional propagation of the mode-converted IBW.",
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{
"category": "Nuclear Fusion System Component",
"entity": "90-degree phased antennas"
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"category": "Plasma dynamic and behavior",
"entity": "directional propagation of the mode-converted IBW"
},
{
"category": "Plasma property",
"entity": "mode-converted IBW"
}
]
},
{
"sentence": "Analysis of heat wave propagation showed no strong inward thermal pinch in off-axis heating of an ohmically-heated target plasma in TFTR.",
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{
"category": "Nuclear Fusion Experimental Facility",
"entity": "TFTR"
},
{
"category": "Nuclear Fusion System Component",
"entity": "target plasma"
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{
"category": "Physical Process",
"entity": "heat wave propagation"
},
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"category": "Plasma property",
"entity": "ohmically-heated"
},
{
"category": "Plasma property",
"entity": "thermal pinch"
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{
"category": "Plasma region",
"entity": "off-axis"
}
]
}
]
},
{
"abstract": "Nontritium-breeding D-T reactors have decisive advantages in minimum size, unit cost, variety of applications, and ease of heat removal over reactors using any other fusion cycle, and significant advantages in environmental and safety characteristics over breeding D-T reactors. Considerations of relative energy production demonstrate that the most favorable source of tritium for a widely deployed system of nontritium-breeding D-T reactors is the very large 10 GW thermal semicatalyzed-deuterium SCD, or sub-SCD reactor, where none of the escaping3He 95 or tritium 25 is reinjected for burn-up. Feasibility of the ignited SCD tokamak reactor requires spatially averaged betas of 15 to 20 with a magnetic field at the TF coils of 1213 T.",
"title": "Fuel provision for nonbreeding deuterium-tritium fusion reactors",
"URL": "http://ui.adsabs.harvard.edu/abs/1982JFuE....2..197J/abstract",
"fields_of_study": [
"Tokamak",
"Nuclear engineering",
"Nuclear physics",
"Fusion power",
"Burnup",
"Helium-3",
"Environmental science",
"Deuterium",
"Tritium",
"Nuclear fusion",
"Neutron flux"
],
"year_published": 1982,
"first_author": "D. L. Jassby",
"scholarly_citations_count": 5,
"NER-RE": [
{
"sentence": "Nontritium-breeding D-T reactors have decisive advantages in minimum size, unit cost, variety of applications, and ease of heat removal over reactors using any other fusion cycle, and significant advantages in environmental and safety characteristics over breeding D-T reactors.",
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"category": "Concept",
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{
"category": "Nuclear Fusion System Component",
"entity": "heat removal"
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{
"category": "Safety Feature and Regulatory Standard",
"entity": "environmental and safety characteristics"
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{
"category": "Chemical Element or Compound",
"entity": "tritium"
}
]
},
{
"sentence": "Considerations of relative energy production demonstrate that the most favorable source of tritium for a widely deployed system of nontritium-breeding D-T reactors is the very large 10 GW thermal semicatalyzed-deuterium SCD, or sub-SCD reactor, where none of the escaping3He 95 or tritium 25 is reinjected for burn-up.",
"entities": [
{
"category": "Particle",
"entity": "Tritium"
},
{
"category": "Particle",
"entity": "Deuterium"
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{
"category": "Particle",
"entity": "3He"
},
{
"category": "Nuclear Fusion Device Type",
"entity": "D-T reactors"
},
{
"category": "Nuclear Fusion System Configuration",
"entity": "Semicatalyzed-deuterium SCD"
},
{
"category": "Nuclear Fusion System Configuration",
"entity": "Sub-SCD reactor"
}
]
},
{
"sentence": "Feasibility of the ignited SCD tokamak reactor requires spatially averaged betas of 15 to 20 with a magnetic field at the TF coils of 1213 T.",
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{
"category": "Nuclear Fusion Device Type",
"entity": "SCD tokamak reactor"
},
{
"category": "Nuclear Fusion System Component",
"entity": "TF coils"
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"category": "Physics Entity",
"entity": "magnetic field"
},
{
"category": "Plasma property",
"entity": "betas"
}
]
}
]
},
{
"abstract": "A flexible direct-drive target platform is used to implode cryogenic deuteriumtritium DT capsules on the OMEGA laser. The goal of these experiments is to demonstrate ignition hydrodynamically equivalent performance where the laser drive intensity, the implosion velocity, the fuel adiabat, and the in-flight aspect ratio IFAR are the same as those for a 1.5-MJ target designed to ignite on the National Ignition Facility. The results from a series of 29 cryogenic DT implosions are presented. The implosions were designed to span a broad region of design space to study target performance as a function of shell stability adiabat and implosion velocity. Ablation-front perturbation growth appears to limit target performance at high implosion velocities. Target outer-surface defects associated with contaminant gases in the DT fuel are identified as the dominant perturbation source at the ablation surface performance degradation is confirmed by 2D hydrodynamic simulations that include these defects. A trend in the value of the Lawson criterion for each of the implosions in adiabatIFAR space suggests the existence of a stability boundary that leads to ablator mixing into the hot spot for the most ignition-equivalent designs.",
"title": "Improving cryogenic deuterium–tritium implosion performance on OMEGAa)",
"URL": "http://ui.adsabs.harvard.edu/abs/2013PhPl...20e6317S/abstract",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Ignition system",
"Lawson criterion",
"Cryogenics",
"Atomic physics",
"Implosion",
"National Ignition Facility",
"Laser ablation",
"Computational physics",
"Plasma"
],
"year_published": 2013,
"first_author": "T. C. Sangster",
"scholarly_citations_count": 49,
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"entity": "cryogenic deuterium-tritium (DT) capsules"
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"category": "Nuclear Fusion Technique",
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}
]
},
{
"sentence": "The goal of these experiments is to demonstrate ignition hydrodynamically equivalent performance where the laser drive intensity, the implosion velocity, the fuel adiabat, and the in-flight aspect ratio IFAR are the same as those for a 1.5-MJ target designed to ignite on the National Ignition Facility.",
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]
},
{
"sentence": "The results from a series of 29 cryogenic DT implosions are presented.",
"entities": [
{
"category": "Nuclear Fusion Technique",
"entity": "cryogenic DT implosions"
},
{
"category": "Experimental Apparatus",
"entity": "cryogenic system"
},
{
"category": "Particle",
"entity": "DT (Deuterium-Tritium)"
}
]
},
{
"sentence": "The implosions were designed to span a broad region of design space to study target performance as a function of shell stability adiabat and implosion velocity.",
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{
"category": "Nuclear Fusion System Component",
"entity": "shell"
},
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"category": "Physics Entity",
"entity": "adiabat"
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{
"category": "Physics Entity",
"entity": "implosion velocity"
},
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"category": "Plasma property",
"entity": "target"
}
]
},
{
"sentence": "Ablation-front perturbation growth appears to limit target performance at high implosion velocities.",
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"category": "Physical Process",
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"entity": "implosion velocities"
}
]
},
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"sentence": "Target outer-surface defects associated with contaminant gases in the DT fuel are identified as the dominant perturbation source at the ablation surface performance degradation is confirmed by 2D hydrodynamic simulations that include these defects.",
"entities": [
{
"category": "Nuclear Fusion System Component",
"entity": "ablation surface"
},
{
"category": "Nuclear Fusion System Component",
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"entity": "DT fuel"
},
{
"category": "Physical Process",
"entity": "ablation"
},
{
"category": "Plasma property",
"entity": "performance degradation"
},
{
"category": "Software and simulation",
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},
{
"category": "Nuclear Fusion System Component",
"entity": "DT fuel"
}
]
},
{
"sentence": "A trend in the value of the Lawson criterion for each of the implosions in adiabatIFAR space suggests the existence of a stability boundary that leads to ablator mixing into the hot spot for the most ignition-equivalent designs.",
"entities": [
{
"category": "Concept",
"entity": "Lawson criterion"
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{
"category": "Concept",
"entity": "ignition"
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{
"category": "Plasma region",
"entity": "hot spot"
},
{
"category": "Plasma dynamic and behavior",
"entity": "ablator mixing"
},
{
"category": "Nuclear Fusion System Configuration",
"entity": "implosions in adiabatIFAR space"
}
]
}
]
},
{
"abstract": "The observation of internal transport barriers ITBs in which ion thermal diffusivity is reduced to a neoclassical level has been made for the first time in tokamak plasmas fueled with deuterium and tritium ions using a broad current density profile. The heating and current profiles required to obtain an ITB are similar in D-T and D-D plasmas. Central ion temperatures of 40 keV and plasma pressure gradients of were observed in a D-T plasma, leading to a fusion triple product and 8.2 MW of fusion power. There is potential for further optimization as a step towards the development of efficient tokamak fusion reactors.",
"title": "INTERNAL TRANSPORT BARRIERS IN JET DEUTERIUM-TRITIUM PLASMAS",
"URL": "https://ui.adsabs.harvard.edu/abs/1998PhRvL..80.5544G/abstract",
"fields_of_study": [
"Tokamak",
"Physics",
"Ion",
"Atomic physics",
"Current density",
"Fusion power",
"Triple product",
"Deuterium",
"Plasma",
"Atmospheric-pressure plasma"
],
"year_published": 1998,
"first_author": "C. Gormezano",
"scholarly_citations_count": 123,
"NER-RE": [
{
"sentence": "The observation of internal transport barriers ITBs in which ion thermal diffusivity is reduced to a neoclassical level has been made for the first time in tokamak plasmas fueled with deuterium and tritium ions using a broad current density profile.",
"entities": [
{
"category": "Nuclear Fusion Device Type",
"entity": "tokamak"
},
{
"category": "Plasma property",
"entity": "internal transport barriers"
},
{
"category": "Plasma property",
"entity": "ion thermal diffusivity"
},
{
"category": "Chemical Element or Compound",
"entity": "deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Plasma dynamic and behavior",
"entity": "neoclassical level"
},
{
"category": "Nuclear Fusion System Configuration",
"entity": "broad current density profile"
}
]
},
{
"sentence": "The heating and current profiles required to obtain an ITB are similar in D-T and D-D plasmas.",
"entities": [
{
"category": "Plasma property",
"entity": "ITB"
},
{
"category": "Chemical Element or Compound",
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},
{
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"entity": "D-D"
}
]
},
{
"sentence": "Central ion temperatures of 40 keV and plasma pressure gradients of were observed in a D-T plasma, leading to a fusion triple product and 8.2 MW of fusion power.",
"entities": [
{
"category": "Plasma property",
"entity": "plasma pressure gradients"
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"category": "Physics Entity",
"entity": "ion temperatures"
},
{
"category": "Physics Entity",
"entity": "fusion triple product"
},
{
"category": "Physics Entity",
"entity": "fusion power"
},
{
"category": "Chemical Element or Compound",
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}
]
},
{
"sentence": "There is potential for further optimization as a step towards the development of efficient tokamak fusion reactors.",
"entities": [
{
"category": "Nuclear Fusion Device Type",
"entity": "tokamak"
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{
"category": "Concept",
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]
}
]
},
{
"abstract": "We report an increase in an emission from solid deuterium tritium at 825 nm, while pumping an electron bubble transition centered at ensuremath350 nm. This experiment implies unbound electrons cause the emission at 825 nm. We find this steady-state emission shifts 8 nm towards longer wavelengths upon increasing the temperature from 4.5 to 10 K. Finally, the same emission in pure solid is shifted 3 nm towards longer wavelengths and contains a triplet structure similar to the triplet structure observed in absorption measurements of the 1S to 1P transition of electron bubbles.",
"title": "Optical emission from electrons in solid deuterium tritium.",
"URL": "https://journals.aps.org/prb/abstract/10.1103/PhysRevB.49.11817?ft=1",
"fields_of_study": [
"Electron",
"Optical pumping",
"Atomic physics",
"Materials science",
"Electron bubble",
"Atmospheric temperature range",
"Spectral line",
"Deuterium",
"Wavelength",
"Absorption (chemistry)"
],
"year_published": 1994,
"first_author": "F. Magnotta",
"scholarly_citations_count": 2,
"NER-RE": [
{
"sentence": "We report an increase in an emission from solid deuterium tritium at 825 nm, while pumping an electron bubble transition centered at ensuremath350 nm.",
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{
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"entity": "deuterium"
},
{
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"entity": "electron bubble"
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]
},
{
"sentence": "This experiment implies unbound electrons cause the emission at 825 nm.",
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{
"category": "Particle",
"entity": "electrons"
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{
"category": "Physics Entity",
"entity": "emission"
},
{
"category": "Physics Entity",
"entity": "wavelength"
}
]
},
{
"sentence": "We find this steady-state emission shifts 8 nm towards longer wavelengths upon increasing the temperature from 4.5 to 10 K. Finally, the same emission in pure solid is shifted 3 nm towards longer wavelengths and contains a triplet structure similar to the triplet structure observed in absorption measurements of the 1S to 1P transition of electron bubbles.",
"entities": [
{
"category": "Physics Entity",
"entity": "electron bubbles"
},
{
"category": "Physical Process",
"entity": "absorption"
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{
"category": "Physical Process",
"entity": "emission"
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{
"category": "Physics Entity",
"entity": "triplet structure"
},
{
"category": "Physics Entity",
"entity": "1S to 1P transition"
}
]
}
]
},
{
"abstract": "Purely alpha-particle-driven Toroidal Alfven Eigenmodes TAEs with toroidal mode numbers n1-6 have been observed in Deuterium-Tritium D-T plasmas on the Tokamak Fusion Test Reactor. The appearance of mode activity following termination of neutral beam injection in plasmas with q01 is generally consistent with theoretical predictions of TAE stability. Internal reflectometer measurements of TAE activity is compared with theoretical calculations of the radial mode structure. Core localization of the modes to the region of reduced central magnetic shear is confirmed, however the mode structure can deviate significantly from theoretical estimates. The peak measured TAE amplitude of delta nn10superscript-4 at ra0.3-0.4 corresponds to delta BB10-5, while dBB10superscript-8 is measured at the plasma edge. Enhanced alpha particle loss associated with TAE activity has not been observed.",
"title": "Toroidal Alfvén eigenmodes in TFTR deuterium–tritium plasmas",
"URL": "https://inis.iaea.org/Search/search.aspx?orig_q=RN:29047956",
"fields_of_study": [
"Physics",
"Ion",
"Amplitude",
"Atomic physics",
"Neutral beam injection",
"Tokamak Fusion Test Reactor",
"Charged particle",
"Plasma diagnostics",
"Alpha particle",
"Plasma"
],
"year_published": 1998,
"first_author": "Raffi Nazikian",
"scholarly_citations_count": 33,
"NER-RE": [
{
"sentence": "Purely alpha-particle-driven Toroidal Alfven Eigenmodes TAEs with toroidal mode numbers n1-6 have been observed in Deuterium-Tritium D-T plasmas on the Tokamak Fusion Test Reactor.",
"entities": [
{
"category": "Nuclear Fusion Device Type",
"entity": "Tokamak"
},
{
"category": "Nuclear Fusion Experimental Facility",
"entity": "Tokamak Fusion Test Reactor"
},
{
"category": "Plasma property",
"entity": "Deuterium-Tritium (D-T) plasmas"
},
{
"category": "Particle",
"entity": "Alpha-particle"
},
{
"category": "Plasma dynamic and behavior",
"entity": "Toroidal Alfven Eigenmodes (TAEs)"
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{
"category": "Physics Entity",
"entity": "Toroidal mode numbers"
}
]
},
{
"sentence": "The appearance of mode activity following termination of neutral beam injection in plasmas with q01 is generally consistent with theoretical predictions of TAE stability.",
"entities": [
{
"category": "Plasma property",
"entity": "mode activity"
},
{
"category": "Nuclear Fusion Technique",
"entity": "neutral beam injection"
},
{
"category": "Plasma property",
"entity": "TAE stability"
},
{
"category": "Theory and Calculation",
"entity": "q0"
},
{
"category": "Theory and Calculation",
"entity": "theoretical predictions"
}
]
},
{
"sentence": "Internal reflectometer measurements of TAE activity is compared with theoretical calculations of the radial mode structure.",
"entities": [
{
"category": "Detection and Monitoring Systems",
"entity": "Internal reflectometer"
},
{
"category": "Plasma property",
"entity": "TAE activity"
},
{
"category": "Theory and Calculation",
"entity": "theoretical calculations of the radial mode structure"
}
]
},
{
"sentence": "Core localization of the modes to the region of reduced central magnetic shear is confirmed, however the mode structure can deviate significantly from theoretical estimates.",
"entities": [
{
"category": "Plasma region",
"entity": "core"
},
{
"category": "Field Configuration",
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{
"category": "Plasma dynamic and behavior",
"entity": "mode structure"
},
{
"category": "Theory and Calculation",
"entity": "theoretical estimates"
}
]
},
{
"sentence": "The peak measured TAE amplitude of delta nn10superscript-4 at ra0.3-0.4 corresponds to delta BB10-5, while dBB10superscript-8 is measured at the plasma edge.",
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"category": "Plasma property",
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"entity": "delta nn10superscript-4"
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{
"sentence": "Enhanced alpha particle loss associated with TAE activity has not been observed.",
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"category": "Particle",
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},
{
"abstract": "Comparing with ITER, the experimental fusion machine under constraction, the next step test fusion power plant, DEMO will be characterized by very long pulsesteady-state operation and much higher plasma volume and fusion power. The substantially increased level of neutron and gamma fluxes will require reducing the physical access to the plant. It means some conventional diagnostics for the fusion plasma control will be not suitable in DEMO. Development of diagnostics along with the machine design is a primary task for the test plant. The deuterium- tritium fuel ratio and temperature are among important parameters, which should be under control. In this letter a novel technique for the core fuel ratio and temperature diagnostics is proposed. It is based on measurements and comparison of the rates Tp,4He and DT,5He nuclear reactions that take place in the hot deuterium-tritium plasma. Based on detection of high energy gamma-rays, this diagnostic is robust, efficient and does not require direct access to the plasma. It could be included in the loop of the burning plasma control system. A feasibility of the diagnostic in experiments on JET and ITER is also discussed.",
"title": "On the Core Deuterium-Tritium Fuel Ratio and Temperature Measurements in DEMO",
"URL": "https://arxiv.org/abs/1406.3174",
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"abstract": "The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Test Reactor TFTR. These activities include preparation of the tritium gas handling system, installation of additional neutron shielding, conversion of the toroidal field coil cooling system from water to a FluorinertTM system, modification of the vacuum system to handle tritium, preparation, and testing of the neutral beam system for tritium operation and a final deuteriumdeuterium DD run to simulate expected deuteriumtritium DT operation. Testing of the tritium system with low concentration tritium has successfully begun. Simulation of trace and high power DT experiments using DD have been performed. The physics objectives of DT operation are production of 10 MW of fusion power, evaluation of confinement, and heating in deuteriumtritium plasmas, evaluation of αparticle heating of electrons, and collective effects driven by alpha particles and testing of diag...",
"title": "Preparations for deuterium-tritium experiments on the Tokamak Fusion Test Reactor*",
"URL": "https://jglobal.jst.go.jp/en/detail?JGLOBAL_ID=201902100080151040",
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"Lawson criterion",
"Nuclear physics",
"Fusion power",
"Tokamak Fusion Test Reactor",
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"Deuterium",
"Tritium",
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"abstract": "A numerical one-dimensional solution of the Euler equations for an imploding spherical tungsten shell with internal deuterium-tritium gas is applied to study impact-fusion dynamics with parameters of fusion-reactor relevance. Thermal conduction and radiative energy loss by the plasma are taken into account, as is heating by fusion-generated alpha particles. A variety of target sizes and impact velocities are examined, and scaling laws for fusion yields are deduced which define possible parameters for conceptual commercial impact-fusion power reactors. It is found that shell energies and velocities of about 30 MJ and 110 kms would be satisfactory. A potential commercial impact-fusion reactor based on such parameters is discussed.",
"title": "Numerical studies of deuterium-tritium ignition in impact-fusion targets",
"URL": "https://ieeexplore.ieee.org/iel1/27/1398/00032256.pdf",
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"Thermal conduction",
"Nuclear physics",
"Materials science",
"Shell (structure)",
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"Euler equations",
"Mechanics",
"Deuterium",
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"abstract": "Thermodynamic estimation is still too much requested for scientific applications in spite of great advances in simulation methods for efficient determination of phase equilibrium of multi-component systems. In this work, thermodynamic properties of deuterium-tritium mixture in a wide range of temperatures and pressures have been predicted. Buckingham exp-6 potential has been utilized in calculations, based on statistical perturbation theory. The effects of various values of density, temperature and isotopic concentrations on pressure have been studied. Eventually, we have found out symmetrical effects of tritium concentration in deuterium-tritium mixtures.",
"title": "Effects of Isotopic Concentrations on Thermodynamic Parameters of Deuterium-Tritium Mixtures",
"URL": "https://iopscience.iop.org/article/10.1088/0253-6102/60/1/15/meta",
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"abstract": "One of the main objectives of the JET experiment is to reach near ignition conditions using deuterium-tritium mixtures so that significant heating of the plasma by alpha particles is achieved. This objective is reflected in the JET development plan which aims at one or two years of active operation and a few thousand deuterium-tritium shots. This approach, where it is believed that a sustained active operation period is necessary for a meaningful study of alpha particle heating, has had considerable design and cost implications on the whole project. The paper first reviews the impact of the active phase on the general design concepts and detailed design of the machine. Buildings, auxiliary systems, power supplies and diagnostics have also been strongly influenced by requirements resulting from the activation of the machine or the use of tritium. The paper reviews also the development programme which is being pursued vigorously in the areas of remote handling and tritium recycling, in readiness for the active phase. An evaluation of the cost of all facilities implemented for the active phase in relation to the overall project cost is also presented.",
"title": "Main Features Implemented in the JET Facility for Deuterium-Tritium Operation",
"URL": "https://www.ans.org/pubs/journals/fst/a_24923",
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"abstract": "The paper presents the results of an experimental study of the shelf life of sealed plasma focus chambers with deuterium-tritium and deuterium fillings. Shelf life is defined as maintaining the level of neutron yield during operation of PF chambers as part of pulsed neutron generators after long storage intervals. The release of impurities from the inner surfaces of the PF chamber and the accumulation of he-lium He3 due to the decay of tritium in the volume of the sealed-off PF chambers leads to a significant decrease in the neutron radiation yield several years after the chamber is filled with the working mixture. The paper shows that the shelf life of the chambers is significantly increased when using a gas generator, in which hy-drogen isotopes are contained in a bound state, and are released into the inner volume of the chamber only for the duration of operation as part of neutron gen-erators. It has been shown experimentally that spherical chambers of the PF9 type provide a level of neutron radiation yield Y, close to the initial value in the manu-facture of chambers, after more than 10 years of storage.",
"title": "Shelf life of plasma focus chambers with deuterium-tritium filling",
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"abstract": "An ultraviolet absorption feature has been seen in solid deuterium-tritium and hydrogen-tritium at a sensor temperature of 5 K. The peak occurs at 3.6 eV and is about 1.5 eV wide. It disappears when the temperature is raised to about 10 K but reappears upon cooling and is, therefore, radiation induced. At 5 K, the absorption line forms on a time scale of minutes and appears to represent part-per-million levels of electron-mass defects. The suggested model is that of a trapped electron, where the absorption line is the ground state-to-the-conduction band transition. A marked isotope effect is seen between D-T and H-T.",
"title": "Ultraviolet Radiation-Damage Absorption Line in Solid Deuterium-Tritium",
"URL": "https://www.ans.org/pubs/journals/fst/a_24615",
"fields_of_study": [
"Absorption spectroscopy",
"Electron",
"Electromagnetic radiation",
"Atomic physics",
"Materials science",
"Stable isotope ratio",
"Spectral line",
"Hydrogen",
"Deuterium",
"Kinetic isotope effect"
],
"year_published": 1985,
"first_author": "Evelyn Fearon",
"scholarly_citations_count": 3,
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"abstract": "The fusion of deuterium D with tritium T is the most promising of the reactions that could power thermonuclear reactors of the future. It may lead to even more efficient energy generation if obtained in a polarized state, that is with the spin of the reactants aligned. Here, we report first-principles predictions of the polarized DT fusion using nuclear forces from effective field theory. By employing the ab initio no-core shell model with continuum reaction method to solve the quantum mechanical five-nucleon problem, we accurately determine the enhanced fusion rate and angular distribution of the emitted neutron and 4He. Our calculations demonstrate in detail the small contribution of anisotropies, placing on a firmer footing the understanding of the rate of DT fusion in a polarized plasma. In the future, analogous calculations could be used to obtain accurate values for other, more uncertain thermonuclear reaction data critical to nuclear science applications. Thermonuclear fusion of nuclei of deuterium and tritium may provide the energy for the future and spin polarization is a potential mechanism for enhancing the nuclear reaction. Here the authors predict the enhanced DT fusion rate using chiral effective field theory and ab initio calculations.",
"title": "Ab initio predictions for polarized deuterium-tritium thermonuclear fusion.",
"URL": "https://www.osti.gov/pages/servlets/purl/1497262",
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"Physics",
"Neutron",
"Ab initio quantum chemistry methods",
"Nuclear physics",
"Nuclear force",
"Nuclear reaction",
"Spin polarization",
"Ab initio",
"Deuterium",
"Thermonuclear fusion",
"Fusion",
"Effective field theory",
"Atomic physics",
"Strong interaction"
],
"year_published": 2019,
"first_author": "Guillaume Hupin",
"scholarly_citations_count": 48,
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"sentence": "Our calculations demonstrate in detail the small contribution of anisotropies, placing on a firmer footing the understanding of the rate of DT fusion in a polarized plasma.",
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"sentence": "In the future, analogous calculations could be used to obtain accurate values for other, more uncertain thermonuclear reaction data critical to nuclear science applications.",
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"sentence": "Thermonuclear fusion of nuclei of deuterium and tritium may provide the energy for the future and spin polarization is a potential mechanism for enhancing the nuclear reaction.",
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"sentence": "Here the authors predict the enhanced DT fusion rate using chiral effective field theory and ab initio calculations.",
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]
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]
},
{
"abstract": "We have examined two of the variables that affect the beta-layering process in which nonuniform layers of solid deuterium-tritium DT are driven toward uniformity by beta-decay induced sublimation...",
"title": "Beta-layering of solid deuterium-tritium in a spherical polycarbonate shell",
"URL": "https://inis.iaea.org/Search/search.aspx?orig_q=RN:24021361",
"fields_of_study": [
"Analytical chemistry",
"Helium-4",
"Layering",
"Atomic physics",
"Materials science",
"Radioactive decay",
"Isotopes of helium",
"Polycarbonate",
"Sublimation (phase transition)",
"Deuterium",
"Tritium"
],
"year_published": 1992,
"first_author": "J. D. Simpson",
"scholarly_citations_count": 7,
"NER-RE": []
},
{
"abstract": "Abstract A baseline scenario of deuterium-tritium D-T plasma with peripheral high field side fuelling pellets has been produced on JET in order to mimic the situation in ITER. The isotope mix ratio is controlled in order to target the value of 50-50 by combination of tritium gas puffing and deuterium pellet injection. Multiple factors controlling the fuelling efficiency of individual pellets are analysed with following findings 1 prompt particle losses due to pellet triggered ELMs are detected, 2 plasmoids drift velocity might be smaller than predicted by simulation, 3 post-pellet particle loss is controlled by transient ELMy phases. Overall pellet particle flux normalised to heat flux is similar to that in previous pellet fuelling experiments on AUG and JET.",
"title": "Fuelling of deuterium-tritium plasma by peripheral pellets in JET experiments",
"URL": "NaN",
"fields_of_study": "NaN",
"year_published": 2024,
"first_author": "Martin Valovic",
"scholarly_citations_count": "NaN",
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"sentence": "Abstract A baseline scenario of deuterium-tritium D-T plasma with peripheral high field side fuelling pellets has been produced on JET in order to mimic the situation in ITER.",
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"sentence": "Multiple factors controlling the fuelling efficiency of individual pellets are analysed with following findings 1 prompt particle losses due to pellet triggered ELMs are detected, 2 plasmoids drift velocity might be smaller than predicted by simulation, 3 post-pellet particle loss is controlled by transient ELMy phases.",
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"sentence": "Overall pellet particle flux normalised to heat flux is similar to that in previous pellet fuelling experiments on AUG and JET.",
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"abstract": "The benefits and limitations arising from the use of polarized deuterium-tritium fuels are assessed for commercial tokamak fusion reactors. The difference in capital costs for a reactor with and without polarized fueling is quantified for two reactors, one with a beta of 0.067 and a major radius of 7 and the second with a beta of 0.25 and a major radius of 5.25 . The change in reactor performance is also quantified. The conclusion is that the sum of all benefits associated with the use of polarized fuels does not result in a significant improvement in the tokamak reactor economics.",
"title": "An evaluation of polarized fuels in a commercial deuterium/tritium tokamak reactor",
"URL": "https://ans.org/pubs/journals/fst/a_24851",
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"Tokamak",
"Capital cost",
"Cryogenics",
"Nuclear physics",
"Materials science",
"Economic analysis",
"Light nucleus",
"Deuterium",
"Tritium",
"Radius"
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"year_published": 1986,
"first_author": "Patricia A. Finn",
"scholarly_citations_count": 6,
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"abstract": "Spectrometry of the neutron emission is discussed as a probe of the fuel ion velocity distribution in tokamak plasmas where the instrumental energy calibration allows determination of Doppler shifts on an absolute scale or relative to the emission of thermal plasma conditions. Such Doppler shifts have been measured for plasmas of different heating methods at the Joint European Torus JET using a neutron spectrometer of the magnetic proton recoil MPR type. The principles of the MPR spectrometer as a rotation diagnostic are discussed together with the results obtained for the JET plasmas. The development potential of neutron spectrometry as a rotation diagnostic at the accuracy level of 1 kms for toroidal and poloidal rotation is projected, especially, for use on burning plasma tokamaks.",
"title": "Neutron emission Doppler-shift measurements in deuterium-tritium plasmas",
"URL": "https://aip.scitation.org/doi/10.1063/1.1149334",
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"Tokamak",
"Physics",
"Doppler effect",
"Neutron",
"Neutron emission",
"Atomic physics",
"Nuclear physics",
"Joint European Torus",
"Neutron spectroscopy",
"Spectrometer",
"Plasma diagnostics"
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"year_published": 1999,
"first_author": "Johan Frenje",
"scholarly_citations_count": 9,
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{
"abstract": "The scalar neutron spectrum per source neutron was measured with a miniature NE-213 spectrometer at several positions in water irradiated with deuterium-tritium neutrons. The measured spectrum was...",
"title": "Fast neutron spectrum in water with a deuterium-tritium neutron source",
"URL": "https://www.ans.org/pubs/journals/nse/a_17311",
"fields_of_study": [
"Physics",
"Neutron",
"Neutron source",
"Nuclear physics",
"Neutron temperature",
"Spectrometer",
"Bonner sphere",
"Neutron time-of-flight scattering",
"Deuterium",
"Neutron stimulated emission computed tomography"
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"year_published": 1985,
"first_author": "Hiroshi Sekimoto",
"scholarly_citations_count": 1,
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"abstract": "Spin polarization of the plasma deuterons and tritons in a magnetic fusion reactor can result in an increase in the fusion reactivity and variation of the angular distribution of emission of the fu...",
"title": "Implications of Polarized Deuterium-Tritium Plasmas for Toroidal Fusion Reactors",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST84-A23090",
"fields_of_study": [
"Toroid",
"Reactivity (chemistry)",
"Fusion",
"Nuclear physics",
"Materials science",
"Spin polarization",
"Fusion power",
"Deuterium",
"Tritium",
"Plasma"
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"year_published": 1984,
"first_author": "B. J. Micklich",
"scholarly_citations_count": 6,
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{
"abstract": "The longitudinal nuclear relaxation times of tritons in equilibrium deuteriumtritium eDT, actually D2DTT2 adsorbed onto amorphous silica aerogel has been measured from 4.2 to 23 K from 0.5 to 6.2 monolayers of coverage. Below 7 K, the relaxation time dramatically increases with decreasing temperature, especially for low coverages. A value of 16 for 0.5 monolayer at 4.2 K may be compared with the usual electric quadrupolequadrupole EQQ determined relaxation time of 0.1 . It is shown that absorption of 10 of the tritium beta particle energy occurs in aerogel fully loaded with DT. This decreases the concentration of J1 T2 and increases the nuclear relaxation time. Similar energy absorption calculations in the thin layers shows that long relaxation times are expected, and that the measured values must be caused by spinlattice relaxation with the aerogel surface. Both temperature7 and exponential mechanisms are considered with no final decision being possible. Electric field gradients from...",
"title": "Nuclear relaxation of deuterium–tritium adsorbed onto silica aerogel",
"URL": "https://avs.scitation.org/doi/10.1116/1.577527",
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"Analytical chemistry",
"Electric field gradient",
"Nuclear physics",
"Chemistry",
"Aerogel",
"Spin–lattice relaxation",
"Relaxation (NMR)",
"Deuterium",
"Tritium",
"Monolayer",
"Absorption (chemistry)"
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"year_published": 1991,
"first_author": "P. C. Souers",
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"entity": "exponential mechanism"
}
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},
{
"abstract": "SummaryIn the ITER fusion experiment the torus vacuum pumping system is mainly involved in pumping plasma exhaust gases consisting of DeuteriumTritium DT and trace quantity of helium. The currently proposed plasma operation plan for the six torus cryopumps is staggered for all fueling rate and plasma durations and therefore variable tritium inventories need to be handled. The ITER cryopumps and the backing vacuum pumping system are custom made tritium compatible pumping trains. Their compliant matrix not only asks for pumping efficiencies and hydrogen confinement but also respecting the specific tritium and deuterium DT inventories for measures on radiation protection and fire safety. In this article, we present a possible operation plan for torus vacuum pumping system in combinations with roughing pump trains for the ITER baseline plasma scenario. The operation of the vacuum system is driven by DT inventories in the different pumps and building sectors.The primary vacuum pump is torus cryogenic pump TCP followed backing roughing pump trains comprise the cryogenic viscous flow compressor CVC, tritium compatible scroll and Roots pumps. The TCPs are regenerated during timed intervals for an uninterrupted and safe torus operation. Next to the demanding long pulse operation 1 hour we present an operation plan for inductive short pulse 450 , hybrid pulse 1000 and dwell time vacuum pumping operations. However, the inductive and hybrid pulses are not as critical as long pulse operation pertaining to tritium and hydrogen inventory management.",
"title": "Vacuum Pumping System for ITER's Deuterium Tritium Operational Campaign",
"URL": "NaN",
"fields_of_study": [
"Cryopump",
"Nuclear engineering",
"Vacuum pump",
"Tritium",
"Joint European Torus",
"Train",
"Deuterium",
"Plasma",
"Fusion power",
"Helium",
"Cryogenics",
"Torus",
"Nuclear physics",
"Tokamak",
"Physics",
"Mechanical engineering",
"Atomic physics",
"Engineering",
"Cartography",
"Geometry",
"Mathematics",
"Quantum mechanics",
"Geography"
],
"year_published": 2022,
"first_author": "Matthias Dremel",
"scholarly_citations_count": "NaN",
"NER-RE": [
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"category": "Nuclear Fusion Experimental Facility",
"entity": "ITER"
},
{
"category": "Nuclear Fusion Device Type",
"entity": "Torus"
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"entity": "Vacuum pumping system"
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"category": "Chemical Element or Compound",
"entity": "Deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "Tritium"
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"category": "Chemical Element or Compound",
"entity": "Helium"
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"category": "Plasma property",
"entity": "Plasma exhaust gases"
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"sentence": "The currently proposed plasma operation plan for the six torus cryopumps is staggered for all fueling rate and plasma durations and therefore variable tritium inventories need to be handled.",
"entities": [
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"category": "Nuclear Fusion Device Type",
"entity": "torus"
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"category": "Experimental Apparatus",
"entity": "cryopumps"
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"entity": "tritium"
},
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"category": "Plasma property",
"entity": "tritium inventories"
}
]
},
{
"sentence": "The ITER cryopumps and the backing vacuum pumping system are custom made tritium compatible pumping trains.",
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{
"category": "Experimental Apparatus",
"entity": "cryopumps"
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{
"category": "Experimental Apparatus",
"entity": "backing vacuum pumping system"
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"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Facility or Institution",
"entity": "ITER"
}
]
},
{
"sentence": "Their compliant matrix not only asks for pumping efficiencies and hydrogen confinement but also respecting the specific tritium and deuterium DT inventories for measures on radiation protection and fire safety.",
"entities": [
{
"category": "Chemical Element or Compound",
"entity": "Tritium"
},
{
"category": "Chemical Element or Compound",
"entity": "Deuterium"
},
{
"category": "Plasma property",
"entity": "Hydrogen confinement"
},
{
"category": "Safety Feature and Regulatory Standard",
"entity": "Radiation protection"
},
{
"category": "Safety Feature and Regulatory Standard",
"entity": "Fire safety"
}
]
},
{
"sentence": "In this article, we present a possible operation plan for torus vacuum pumping system in combinations with roughing pump trains for the ITER baseline plasma scenario.",
"entities": [
{
"category": "Nuclear Fusion Experimental Facility",
"entity": "ITER"
},
{
"category": "Nuclear Fusion System Component",
"entity": "torus vacuum pumping system"
},
{
"category": "Experimental Apparatus",
"entity": "roughing pump trains"
},
{
"category": "Plasma property",
"entity": "baseline plasma scenario"
}
]
},
{
"sentence": "The operation of the vacuum system is driven by DT inventories in the different pumps and building sectors.",
"entities": [
{
"category": "Experimental Apparatus",
"entity": "Vacuum system"
},
{
"category": "Chemical Element or Compound",
"entity": "DT (Deuterium-Tritium)"
}
]
},
{
"sentence": "The primary vacuum pump is torus cryogenic pump TCP followed backing roughing pump trains comprise the cryogenic viscous flow compressor CVC, tritium compatible scroll and Roots pumps.",
"entities": [
{
"category": "Experimental Apparatus",
"entity": "Torus cryogenic pump"
},
{
"category": "Experimental Apparatus",
"entity": "Cryogenic viscous flow compressor"
},
{
"category": "Experimental Apparatus",
"entity": "Tritium compatible scroll"
},
{
"category": "Experimental Apparatus",
"entity": "Roots pumps"
}
]
},
{
"sentence": "The TCPs are regenerated during timed intervals for an uninterrupted and safe torus operation.",
"entities": [
{
"category": "Nuclear Fusion Device Type",
"entity": "torus"
},
{
"category": "Nuclear Fusion System Component",
"entity": "TCPs"
},
{
"category": "Safety Feature and Regulatory Standard",
"entity": "uninterrupted and safe torus operation"
}
]
},
{
"sentence": "Next to the demanding long pulse operation 1 hour we present an operation plan for inductive short pulse 450 , hybrid pulse 1000 and dwell time vacuum pumping operations.",
"entities": [
{
"category": "Nuclear Fusion Technique",
"entity": "inductive short pulse"
},
{
"category": "Nuclear Fusion Technique",
"entity": "hybrid pulse"
},
{
"category": "Experimental Apparatus",
"entity": "vacuum pumping system"
},
{
"category": "Time reference",
"entity": "1 hour"
},
{
"category": "Time reference",
"entity": "450"
},
{
"category": "Time reference",
"entity": "1000"
}
]
},
{
"sentence": "However, the inductive and hybrid pulses are not as critical as long pulse operation pertaining to tritium and hydrogen inventory management.",
"entities": [
{
"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Chemical Element or Compound",
"entity": "hydrogen"
},
{
"category": "Nuclear Fusion Technique",
"entity": "long pulse operation"
},
{
"category": "Nuclear Fusion System Component",
"entity": "inductive pulses"
},
{
"category": "Nuclear Fusion Technique",
"entity": "hybrid pulses"
}
]
}
]
},
{
"abstract": "Spectrometry of the neutron emission has been used to probe the nonthermal features of the fuel ion velocity distributions in tokamak plasmas, especially, those arising from auxiliary heating. The first time resolved measurements are reported from the use of the new magnetic proton recoil MPR spectrometer in observations of deuteriumtritium plasmas at JET with strong ion cyclotron resonance heating. Results from preliminary analysis data are presented and compared with simulated neutron emission spectra based on the assumptions of a thermal plasma a single Maxwellian ion distribution or anisotropic Maxwellians with parallel and perpendicular temperatures, beside their relative amplitudes. The diagnostic results attained are also used to assess the diagnostic capabilities and the potential for use of MPR based diagnostics on burning plasma tokamaks.",
"title": "Neutron spectrometry of radio-frequency heated deuterium–tritium plasmas",
"URL": "https://aip.scitation.org/doi/abs/10.1063/1.1149495",
"fields_of_study": [
"Tokamak",
"Ion",
"Neutron emission",
"Neutron generator",
"Atomic physics",
"Materials science",
"Neutron spectroscopy",
"Plasma diagnostics",
"Nuclear magnetic resonance",
"Deuterium",
"Plasma"
],
"year_published": 1999,
"first_author": "M. Tardocchi",
"scholarly_citations_count": 8,
"NER-RE": [
{
"sentence": "Spectrometry of the neutron emission has been used to probe the nonthermal features of the fuel ion velocity distributions in tokamak plasmas, especially, those arising from auxiliary heating.",
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"entity": "tokamak"
},
{
"category": "Plasma property",
"entity": "nonthermal features of the fuel ion velocity distributions"
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{
"category": "Nuclear Fusion Technique",
"entity": "auxiliary heating"
},
{
"category": "Detection and Monitoring Systems",
"entity": "Spectrometry of the neutron emission"
}
]
},
{
"sentence": "The first time resolved measurements are reported from the use of the new magnetic proton recoil MPR spectrometer in observations of deuteriumtritium plasmas at JET with strong ion cyclotron resonance heating.",
"entities": [
{
"category": "Nuclear Fusion Experimental Facility",
"entity": "JET"
},
{
"category": "Experimental Apparatus",
"entity": "magnetic proton recoil MPR spectrometer"
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{
"category": "Nuclear Fusion Technique",
"entity": "deuterium-tritium plasmas"
},
{
"category": "Physical Process",
"entity": "ion cyclotron resonance heating"
},
{
"category": "Particle",
"entity": "proton"
},
{
"category": "Chemical Element or Compound",
"entity": "deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "tritium"
}
]
},
{
"sentence": "Results from preliminary analysis data are presented and compared with simulated neutron emission spectra based on the assumptions of a thermal plasma a single Maxwellian ion distribution or anisotropic Maxwellians with parallel and perpendicular temperatures, beside their relative amplitudes.",
"entities": [
{
"category": "Concept",
"entity": "thermal plasma"
},
{
"category": "Concept",
"entity": "Maxwellian ion distribution"
},
{
"category": "Concept",
"entity": "anisotropic Maxwellians"
},
{
"category": "Concept",
"entity": "anisotropic Maxwellians"
},
{
"category": "Physics Entity",
"entity": "parallel temperatures"
},
{
"category": "Physics Entity",
"entity": "perpendicular temperatures"
},
{
"category": "Plasma property",
"entity": "neutron emission spectra"
},
{
"category": "Theory and Calculation",
"entity": "simulated neutron emission spectra"
}
]
},
{
"sentence": "The diagnostic results attained are also used to assess the diagnostic capabilities and the potential for use of MPR based diagnostics on burning plasma tokamaks.",
"entities": [
{
"category": "Nuclear Fusion Device Type",
"entity": "Tokamak"
},
{
"category": "Plasma property",
"entity": "burning plasma"
},
{
"category": "Detection and Monitoring Systems",
"entity": "MPR based diagnostics"
}
]
}
]
},
{
"abstract": "Simulation of hydrogen distillation plants requires mathematical procedures suitable for multicomponent systems. In most of the present-day simulation methods a distillation column is assumed to be...",
"title": "Kinetic Method for Hydrogen-Deuterium-Tritium Mixture Distillation Simulation",
"URL": "http://www.osti.gov/scitech/biblio/20854127-kinetic-method-hydrogen-deuterium-tritium-mixture-distillation-simulation",
"fields_of_study": [
"Mass transfer coefficient",
"Fractionating column",
"Packed bed",
"Materials science",
"Distillation",
"Isotope separation",
"Mass transfer",
"Hydrogen",
"Deuterium",
"Thermodynamics"
],
"year_published": 2005,
"first_author": "A. B. Sazonov",
"scholarly_citations_count": 2,
"NER-RE": [
{
"sentence": "Simulation of hydrogen distillation plants requires mathematical procedures suitable for multicomponent systems.",
"entities": [
{
"category": "Chemical Element or Compound",
"entity": "hydrogen"
}
]
},
{
"sentence": "In most of the present-day simulation methods a distillation column is assumed to be...",
"entities": []
}
]
},
{
"abstract": "Fusion-produced alpha particles with energy 0.7 MeV have been spectroscopically observed in the core of a deuterium-tritium plasma in the TFTR tokamak at alpha densities of 310m3. During a sawtooth-free discharge, the measured energy spectra at 0.3 are in good agreement with those predicted on the basis of collisional transport. Time-resolved measurements during the alpha thermalization after alpha source turn-off show decay of the distribution function to lower energies consistent with the classical slowing-down time of 0.5 .",
"title": "Confined alpha distribution measurements in a deuterium-tritium tokamak plasma.",
"URL": "https://link.aps.org/doi/10.1103/PhysRevLett.75.649",
"fields_of_study": [
"Tokamak",
"Physics",
"Thermalisation",
"Atomic physics",
"Energy (signal processing)",
"Distribution function",
"Spectral line",
"Deuterium",
"Alpha particle",
"Plasma"
],
"year_published": 1995,
"first_author": "G. R. McKee",
"scholarly_citations_count": 52,
"NER-RE": [
{
"sentence": "Fusion-produced alpha particles with energy 0.7 MeV have been spectroscopically observed in the core of a deuterium-tritium plasma in the TFTR tokamak at alpha densities of 310m3.",
"entities": [
{
"category": "Particle",
"entity": "alpha particles"
},
{
"category": "Nuclear Fusion Device Type",
"entity": "tokamak"
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{
"category": "Facility or Institution",
"entity": "TFTR"
},
{
"category": "Plasma region",
"entity": "core"
},
{
"category": "Chemical Element or Compound",
"entity": "deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Plasma property",
"entity": "plasma density"
}
]
},
{
"sentence": "During a sawtooth-free discharge, the measured energy spectra at 0.3 are in good agreement with those predicted on the basis of collisional transport.",
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"category": "Plasma property",
"entity": "sawtooth-free discharge"
},
{
"category": "Physical Process",
"entity": "collisional transport"
},
{
"category": "Theory and Calculation",
"entity": "predicted energy spectra"
}
]
},
{
"sentence": "Time-resolved measurements during the alpha thermalization after alpha source turn-off show decay of the distribution function to lower energies consistent with the classical slowing-down time of 0.5 .",
"entities": [
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"category": "Physical Process",
"entity": "alpha thermalization"
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"category": "Physics Entity",
"entity": "distribution function"
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{
"category": "Particle",
"entity": "alpha"
},
{
"category": "Plasma property",
"entity": "classical slowing-down time"
}
]
}
]
},
{
"abstract": "Tritium permeation at 350C through stainless steel wall of a vessel filled with deuterium-tritium gas of 6.1 106 Pa pressure was practically suppressed by Au plating of 20μm thick applied to the outside surface. The apparent diffusivity of hydrogen through plated Au layer, derived from the experimental data, was 2 1011 cm2s for 470C, which is 105106 times smaller than what would be expected from values reported for wrought Au, and the apparent solubility was very significantly higher than similarly expected level. Gas analysis of the Au layer indicated that the effective suppression of tritium permeation is attributable to trapping of hydrogen by C contained in the Au as impurity. Adequate tightness against tritium leakage has been achieved by Au plating on a vessel used for loading glass microspheres with deuterium-tritium gas, intended for laser fusion targets.",
"title": "Development of Deuterium-Tritium Loading Vessel for Laser Fusion Target",
"URL": "https://www.tandfonline.com/doi/pdf/10.1080/18811248.1986.9735033?needAccess=true",
"fields_of_study": [
"Tritium",
"Deuterium",
"Hydrogen",
"Radiochemistry",
"Impurity",
"Fusion power",
"Permeation",
"Thermal diffusivity",
"Materials science",
"Chemistry",
"Layer (electronics)",
"Solubility",
"Tritium illumination",
"Analytical Chemistry (journal)",
"Nuclear physics",
"Plasma",
"Composite material",
"Chromatography",
"Physics",
"Biochemistry",
"Organic chemistry",
"Quantum mechanics",
"Membrane"
],
"year_published": 1986,
"first_author": "Takayoshi NORIMATSU",
"scholarly_citations_count": 1,
"NER-RE": [
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"category": "Nuclear Fusion System Component",
"entity": "stainless steel wall"
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{
"category": "Nuclear Fusion System Component",
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"category": "Chemical Element or Compound",
"entity": "deuterium"
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{
"category": "Chemical Element or Compound",
"entity": "tritium"
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"category": "Chemical Element or Compound",
"entity": "Au"
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"category": "Physical Process",
"entity": "permeation"
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"sentence": "The apparent diffusivity of hydrogen through plated Au layer, derived from the experimental data, was 2 1011 cm2s for 470C, which is 105106 times smaller than what would be expected from values reported for wrought Au, and the apparent solubility was very significantly higher than similarly expected level.",
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"sentence": "Gas analysis of the Au layer indicated that the effective suppression of tritium permeation is attributable to trapping of hydrogen by C contained in the Au as impurity.",
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{
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"entity": "tritium"
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"sentence": "Adequate tightness against tritium leakage has been achieved by Au plating on a vessel used for loading glass microspheres with deuterium-tritium gas, intended for laser fusion targets.",
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"category": "Chemical Element or Compound",
"entity": "deuterium-tritium gas"
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{
"category": "Chemical Element or Compound",
"entity": "tritium"
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{
"category": "Chemical Element or Compound",
"entity": "Au"
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{
"category": "Nuclear Fusion System Component",
"entity": "vessel"
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{
"category": "Experimental Apparatus",
"entity": "laser"
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{
"category": "Nuclear Fusion Technique",
"entity": "laser fusion"
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{
"category": "Particle",
"entity": "tritium"
},
{
"category": "Nuclear Fusion System Component",
"entity": "glass microspheres"
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]
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},
{
"abstract": "There is a large region of density-temperature space in which the effects of a magnetic field on heat transport and alpha-particle mobility are significant and the magnetic pressure is small compared with the pressure of a deuterium-tritium plasma. Spherical fusion burn in this regime is examined. It is found that for volume burn, magnetic fields can greatly increase the yield. In regimes where propagating burn does not occur, the burn can be enhanced by a magnetic field. In regimes where propagating deflagration would normally occur in the absence of a magnetic field, magnetic fields actually degrade the cross-field propagation. A detonation wave is harder to ignite in the presence of a magnetic field. Once a detonation wave is ignited, no change in the propagation speed is produced by applying a magnetic field.",
"title": "The physics of burn in magnetized deuterium-tritium plasmas: spherical geometry",
"URL": "http://iopscience.iop.org/article/10.1088/0029-5515/26/2/001/meta",
"fields_of_study": [
"Magnetic field",
"Physics",
"Atomic physics",
"Detonation",
"Volume (thermodynamics)",
"Magnetic pressure",
"Deflagration",
"Mechanics",
"Deuterium",
"Spherical geometry",
"Plasma"
],
"year_published": 1986,
"first_author": "Roger Jones",
"scholarly_citations_count": 43,
"NER-RE": [
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{
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"sentence": "It is found that for volume burn, magnetic fields can greatly increase the yield.",
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}
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"sentence": "In regimes where propagating burn does not occur, the burn can be enhanced by a magnetic field.",
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"entity": "propagating burn"
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"sentence": "In regimes where propagating deflagration would normally occur in the absence of a magnetic field, magnetic fields actually degrade the cross-field propagation.",
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"sentence": "A detonation wave is harder to ignite in the presence of a magnetic field.",
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"sentence": "Once a detonation wave is ignited, no change in the propagation speed is produced by applying a magnetic field.",
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"category": "Physical Process",
"entity": "detonation wave"
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},
{
"abstract": "Calculations have been performed to assess the effects of fast-neutron-induced transmutation reactions in the blanket region surrounding the plasma in a Tokamak fusion reactor. The production of bo...",
"title": "Transmutations, Radioactivity, and Afterheat in a Deuterium-Tritium Tokamak Fusion Reactor",
"URL": "http://www.osti.gov/scitech/biblio/4273947-transmutations-radioactivity-afterheat-deuterium-tritium-tokamak-fusion-reactor",
"fields_of_study": [
"Tokamak",
"Nuclear transmutation",
"Radiochemistry",
"Neutron source",
"Neutron generator",
"Materials science",
"Blanket",
"Helium",
"Deuterium",
"Tritium"
],
"year_published": 1974,
"first_author": "W.F. Vogelsang",
"scholarly_citations_count": 31,
"NER-RE": [
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"sentence": "Calculations have been performed to assess the effects of fast-neutron-induced transmutation reactions in the blanket region surrounding the plasma in a Tokamak fusion reactor.",
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"entity": "Tokamak"
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"entity": "blanket region"
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"entity": "fast-neutron-induced transmutation reactions"
},
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"entity": "Calculations"
},
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"category": "Nuclear Fusion System Component",
"entity": "plasma"
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},
{
"abstract": "The paper discusses a numerical model for radial transport in a toroidal plasmagas mixture consisting of all charge states of deuterium, tritium and helium. Solutions of the steady-state momentum and particle balances indicate an enrichment of tritium gas near the reactor wall compared with deuterium. The helium enrichment ratio, although depending strongly on the ion transport model adopted, is always less than unity. Therefore, pumping helium from a cool plasmagas blanket surrounding the entire plasma body is not attractive.",
"title": "Transport properties of a deuterium, tritium, helium plasma/gas mixture",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/25/7/003",
"fields_of_study": [
"Lawson criterion",
"Atomic physics",
"Materials science",
"Ionization",
"Blanket",
"Helium",
"Deuterium",
"Tritium",
"Plasma",
"Tritium illumination"
],
"year_published": 1985,
"first_author": "J.H.H.M. Potters",
"scholarly_citations_count": 10,
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"entity": "deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Chemical Element or Compound",
"entity": "helium"
},
{
"category": "Plasma dynamic and behavior",
"entity": "radial transport"
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"category": "Plasma property",
"entity": "charge states"
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{
"category": "Theory and Calculation",
"entity": "numerical model"
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]
},
{
"sentence": "Solutions of the steady-state momentum and particle balances indicate an enrichment of tritium gas near the reactor wall compared with deuterium.",
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"category": "Particle",
"entity": "tritium"
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{
"sentence": "The helium enrichment ratio, although depending strongly on the ion transport model adopted, is always less than unity.",
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"sentence": "Therefore, pumping helium from a cool plasmagas blanket surrounding the entire plasma body is not attractive.",
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{
"abstract": "Tritium permeation at 350C through stainless steel wall of a vessel filled with deuterium-tritium gas of 6.1 106 Pa pressure was practically suppressed by Au plating of 20μm thick applied to the outside surface. The apparent diffusivity of hydrogen through plated Au layer, derived from the experimental data, was 2 1011 cm2s for 470C, which is 105106 times smaller than what would be expected from values reported for wrought Au, and the apparent solubility was very significantly higher than similarly expected level. Gas analysis of the Au layer indicated that the effective suppression of tritium permeation is attributable to trapping of hydrogen by C contained in the Au as impurity. Adequate tightness against tritium leakage has been achieved by Au plating on a vessel used for loading glass microspheres with deuterium-tritium gas, intended for laser fusion targets.",
"title": "Development of Deuterium-Tritium Loading Vessel for Laser Fusion Target",
"URL": "https://www.tandfonline.com/doi/pdf/10.1080/18811248.1986.9735033",
"fields_of_study": [
"Inertial confinement fusion",
"Radiochemistry",
"Materials science",
"Glass microsphere",
"Thermal diffusivity",
"Permeation",
"Hydrogen",
"Deuterium",
"Tritium",
"Impurity"
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"year_published": 1986,
"first_author": "Takayoshi Norimatsu",
"scholarly_citations_count": 1,
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"abstract": "At the Swiss Federal Institute of Technology, an experimental fusion and fusion-fission hybrid reactor facility is near completion. Experiments are scheduled to begin in February 1984. The experimental cavity leads one to plan experiments mostly with blankets in plane geometry. Five different hybrid blanket modules in plane geometry are analyzed with two different left boundary conditions representing varying experimental situations. Numbers I and II represent energy and fissile fuel producing blankets, whereas number III is mainly a fissile fuel producing blanket. Numbers IV and V are actinide burning blankets. It is shown that the overall neutronic performance, such as sub eff, energy multiplication factor M, fusile and fissile breeding, of a hybrid blanket with transplutonium actinide fuel is already better than that of a UOsub 2 or ThOsub 2 hybrid blanket. Furthermore, the transplutonium actinide waste is partly converted into precious nuclear fuel of a new type, such as sup 242m Am and sup 245Cm. An experimental blanket with a vacuum left boundary has a harder neutron spectrum, and also excessive neutron leakage from the front surface and the lateral surfaces, as compared to that in the blanket in confinement geometry. It leads to the poorer neutronic performancemore of the former. less",
"title": "Neutronics Analysis of Deuterium-Tritium-Driven Experimental Hybrid Blankets",
"URL": "https://ans.org/pubs/journals/fst/a_23124",
"fields_of_study": [
"Actinide",
"Neutron",
"Nuclear physics",
"Materials science",
"Nuclear reaction",
"Uranium dioxide",
"Blanket",
"Nuclear fuel",
"Neutron transport",
"Fissile material"
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"year_published": 1984,
"first_author": "Sümer Şahin",
"scholarly_citations_count": 12,
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"abstract": "Confined trapped alpha energy spectra and differential radial density profiles in TFTR D-T plasmas were obtained with the pellet charge exchange PCX diagnostic, which measures high energy Eα 0.5-3.5 MeV trapped alphas vv-0.048 at a single time slice Δt 1 ms with a spatial resolution of Δr 5 cm. Tritons produced in D-D plasmas and RF driven ion tails H, 3He or T were also observed and energetic tritium ion tail measurements are discussed. PCX alpha and triton energy spectra extending up to their birth energies were measured in the core of MHD quiescent discharges where the expected classical slowing down and pitch angle scattering effects are not complicated by stochastic ripple diffusion and sawtooth activity. Both the shape of the measured alpha and triton energy distributions and their density ratios are in good agreement with TRANSP predictions, indicating that the PCX measurements are consistent with classical thermalization of the fusion generated alphas and tritons. From calculations, these results set an upper limit on possible anomalous radial diffusion for trapped alphas of Dα 0.01 m2s-1. Outside the core, where the trapped alphas are influenced by stochastic ripple diffusion effects, the PCX measurements are consistent with the functional dependence of the Goldston-White-Boozer stochastic ripple threshold on the alpha energy and the profile. In the presence of strong sawtooth activity, the PCX diagnostic observes significant redistribution of the alpha signal radial profile wherein alphas are depleted in the core and redistributed to well outside the 1 radius, but apparently not beyond the energy dependent stochastic ripple loss boundary. The helical electric field produced during the sawtooth crash plays an essential role in modelling the sawtooth redistribution data. In sawtooth free discharge scenarios with reversed shear operation, the PCX diagnostic also observes radial profiles of the alpha signal that are significantly broader than those for supershots. ORBIT modelling of reversed shear and monotonic shear discharges is in agreement with the dependent alpha profiles observed. Redistribution of trapped alpha particles in the presence of core localized toroidal Alfven eigenmode TAE activity was observed and modelling of the PCX measurements based on a synergism involving the α-TAE resonance and the effect of stochastic ripple diffusion is in progress.",
"title": "Confined trapped alpha behaviour in TFTR deuterium-tritium plasmas",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/38/9/303/pdf",
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"Physics",
"Ion",
"Sawtooth wave",
"Thermalisation",
"Atomic physics",
"Scattering",
"Ripple",
"Magnetohydrodynamics",
"Alpha particle",
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"year_published": 1998,
"first_author": "S. S. Medley",
"scholarly_citations_count": 16,
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{
"abstract": "High fusion power experiments using DT mixtures in ELM-free H mode and optimized shear regimes in JET are reported. A fusion power of 16.1 MW has been produced in an ELM-free H mode at 4.2 MA3.6 T. The transient value of the fusion amplification factor was 0.950.17, consistent with the high value of nDT0τEdiaTi0 8.7 102020 -3 keV, and was maintained for about half an energy confinement time until excessive edge pressure gradients resulted in discharge termination by MHD instabilities. The ratio of DD to DT fusion powers from separate but otherwise similar discharges showed the expected factor of 210, validating DD projections of DT performance for similar pressure profiles and good plasma mixture control, which was achieved by loading the vessel walls with the appropriate DT mix. Magnetic fluctuation spectra showed no evidence of Alfvenic instabilities driven by alpha particles, in agreement with theoretical model calculations. Alpha particle heating has been unambiguously observed, its effect being separated successfully from possible isotope effects on energy confinement by varying the tritium concentration in otherwise similar discharges. The scan showed that there was no, or at most a very weak, isotope effect on the energy confinement time. The highest electron temperature was clearly correlated with the maximum alpha particle heating power and the optimum DT mixture the maximum increase was 1.30.23 keV with 1.3 MW of alpha particle heating power, consistent with classical expectations for alpha particle confinement and heating. In the optimized shear regime, clear internal transport barriers were established for the first time in DT, with a power similar to that required in DD. The ion thermal conductivity in the plasma core approached neoclassical levels. Real time power control maintained the plasma core close to limits set by pressure gradient driven MHD instabilities, allowing 8.2 MW of DT fusion power with nDT0τEdiaTi0 1021 -3 keV, even though full optimization was not possible within the imposed neutron budget. In addition, quasi-steady-state discharges with simultaneous internal and edge transport barriers have been produced with high confinement and a fusion power of up to 7 MW these double barrier discharges show a great potential for steady state operation. 1999, Euratom",
"title": "High fusion performance from deuterium-tritium plasmas in JET",
"URL": "https://ui.adsabs.harvard.edu/abs/1999NucFu..39..209K/abstract",
"fields_of_study": [
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"Atomic physics",
"Materials science",
"Electron temperature",
"Fusion power",
"Magnetohydrodynamics",
"Steady state",
"Alpha particle",
"Nuclear fusion",
"Plasma"
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"year_published": 1999,
"first_author": "M. Keilhacker",
"scholarly_citations_count": 245,
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"sentence": "In the optimized shear regime, clear internal transport barriers were established for the first time in DT, with a power similar to that required in DD.",
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"sentence": "The ion thermal conductivity in the plasma core approached neoclassical levels.",
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"sentence": "Real time power control maintained the plasma core close to limits set by pressure gradient driven MHD instabilities, allowing 8.2 MW of DT fusion power with nDT0τEdiaTi0 1021 -3 keV, even though full optimization was not possible within the imposed neutron budget.",
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"sentence": "In addition, quasi-steady-state discharges with simultaneous internal and edge transport barriers have been produced with high confinement and a fusion power of up to 7 MW these double barrier discharges show a great potential for steady state operation.",
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"abstract": "Cryogenic-deuterium-tritium DT target compression experiments with low-adiabat alpha, multiple-shock drive pulses have been performed on the Omega Laser Facility to demonstrate hydrodynamic-equivalent ignition performance. The multiple-shock drive pulse facilitates experimental shock tuning using an established cone-in-shell target platform. These shock-tuned drive pulses have been used to implode cryogenic-DT targets with peak implosion velocities of 3x10 cms at peak drive intensities of 8x10 Wcm. During a recent series of alphaapprox2 implosions, one of the two necessary conditions for initiating a thermonuclear burn wave in a DT plasma was achieved an areal density of approximately 300 mgcm was inferred using the magnetic recoil spectrometer. The other condition--a burn-averaged ion temperature of 8-10 keV--cannot be achieved on Omega because of the limited laser energy the kinetic energy of the imploding shell is insufficient to heat the plasma to these temperatures. A of approximately 3.4 keV wouldmore be required to demonstrate ignition hydrodynamic equivalence. The reached during the recent series of alphaapprox2 implosions was approximately 2 keV, limited primarily by laser-drive and target nonuniformities. Work is underway to improve drive and target symmetry for future experiments. less",
"title": "Shock-tuned cryogenic-deuterium-tritium implosion performance on Omega",
"URL": "https://scitation.aip.org/content/aip/journal/pop/17/5/10.1063/1.3360928",
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"Inertial confinement fusion",
"Physics",
"Kinetic energy",
"Atomic physics",
"Nuclear physics",
"Implosion",
"Recoil",
"Omega",
"Plasma diagnostics",
"Shock wave",
"Thermonuclear fusion"
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"year_published": 2010,
"first_author": "T. C. Sangster",
"scholarly_citations_count": 36,
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"sentence": "The other condition--a burn-averaged ion temperature of 8-10 keV--cannot be achieved on Omega because of the limited laser energy the kinetic energy of the imploding shell is insufficient to heat the plasma to these temperatures.",
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"abstract": "AbstractInertial confinement fusion requires very smooth and uniform solid deuterium-tritium D-T fuel layers. The National Ignition Facility NIF point design calls for a 65- to 75-μm-thick D-T fuel layer inside of a 2-mm-diam spherical ablator shell to be 1.5 K below the D-T melting temperature Tm of 19.79 K. We find that the layer quality depends on the initial crystal seeding, with the best layers grown from a single seed. The low modes of the layer are controlled by thermal shimming of the hohlraum and meet the NIF requirement with beryllium shells and nearly meet the requirement with plastic shells. The remaining roughness is localized in grain-boundary grooves and is minimal for a single crystal layer. Once formed, the layers need to be cooled to Tm- 1.5 K. We have studied dependence of the roughness on the cooling rate and found that cooling at rates of 0.03 to 0.5 Ks is able to preserve the layer structure for a few seconds after reaching the desired temperature. The entire fuel layer remai...",
"title": "Deuterium-Tritium Fuel Layer Formation for the National Ignition Facility",
"URL": "https://www.ans.org/pubs/journals/taf/article-11497/",
"fields_of_study": [
"Composite material",
"Atomic physics",
"Materials science",
"Thermal",
"National Ignition Facility",
"Layer (electronics)",
"Beryllium",
"Hohlraum",
"Crystal",
"Surface finish",
"Single crystal"
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"year_published": 2011,
"first_author": "B. J. Kozioziemski",
"scholarly_citations_count": 46,
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"sentence": "The National Ignition Facility NIF point design calls for a 65- to 75-μm-thick D-T fuel layer inside of a 2-mm-diam spherical ablator shell to be 1.5 K below the D-T melting temperature Tm of 19.79 K. We find that the layer quality depends on the initial crystal seeding, with the best layers grown from a single seed.",
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"abstract": "AbstractThe impact ignition model is proposed based on the collision of a deuteriumtritium DT layer accelerated to high velocities in a conical target. Simple mechanism, low cost, high coupling efficiency, and lack of the need for Petawatt laser pulses are the prominent advantages of this model. However, an increase in the productivity of this ignition mechanism is an important issue. In this regard, in this paper, the idea of impact ignition using the plasma degeneracy mechanism has been investigated. For this purpose, first, the ignition energy gain and stopping power of the DT beam in pure and impure fuels, by employing both degenerate and nondegenerate plasmas, have been examined numerically. Then, in order to assess the penetration depth and range of the incident beam, simulations have been carried out using a threedimensional 3D Monte Carlo code for two states of degenerate and nondegenerate precompressed pure fuel. The results imply that the state of degeneracy causes an increase by about 63 in the energy gain of impact ignition. In addition, the degeneracy condition leads to an approximate enhancement of 60 in the energy deposition of the pure fuel and about 67 for the impure fuel, with a mixed density ratio of 1.5 therefore, the range and penetration depth decrease significantly in comparison to the nondegenerate one. This can be indicative of the increasing efficiency of impact ignition conditions in the presence of degenerate plasma. The results of the range for the pure fuel have also been confirmed by a 3D Monte Carlo simulation code.",
"title": "Deuterium‐tritium fuel impact ignition in the presence of degenerate plasma",
"URL": "https://onlinelibrary.wiley.com/doi/abs/10.1002/ctpp.202000188",
"fields_of_study": [
"Stopping power (particle radiation)",
"Ignition system",
"Atomic physics",
"Materials science",
"Penetration depth",
"Deuterium",
"Tritium",
"Degenerate energy levels",
"Plasma"
],
"year_published": 2021,
"first_author": "Seddigheh Pourhosseini",
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"sentence": "Then, in order to assess the penetration depth and range of the incident beam, simulations have been carried out using a threedimensional 3D Monte Carlo code for two states of degenerate and nondegenerate precompressed pure fuel.",
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{
"abstract": "During the initial deuterium-tritium experiments on TFTR, neutron emission was measured with U and U fission chambers, silicon surface barrier diodes, spatially collimated He proportional counters and ZnS scintillators, and a variety of elemental activation foils. The activation foils, He counters and silicon diodes can discriminate between 14 MeV and 2.5 MeV neutrons. The other detectors respond to both DD and DT neutrons but are more sensitive to the latter. The proportional counters, scintillators, and some of the fission chambers were calibrated absolutely, using a 14-MeV neutron generator positioned at numerous locations inside the TFTR vacuum vessel. Although the directly calibrated systems were saturated during the highest power deuterium-tritium operation, they allowed cross-calibration of less sensitive fission chambers and silicon diodes. The estimated absolute accuracy of the uncertainty-weighted mean of these cross-calibrations, combined with an independent calibration derived from activation foil determinations of total neutron yield, is 7.",
"title": "Cross-calibration of neutron detectors for deuterium-tritium operation in TFTR",
"URL": "https://ui.adsabs.harvard.edu/abs/1995RScI...66..894J/abstract",
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"Physics",
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"Neutron",
"Neutron emission",
"Scintillator",
"Neutron generator",
"Nuclear physics",
"Scintillation counter",
"Deuterium",
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"year_published": 1995,
"first_author": "L. C. Johnson",
"scholarly_citations_count": 30,
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"abstract": "High gain targets for inertial confinement fusion ICF are spherical shells which contain a layer of deuterium-tritium DT ice which surrounds a volume of DT gas in thermal equilibrium with the solid. The roughness of the inner surface of the cryogenic fuel layer inside of these targets is one of the sources of imperfections which cause implosions to deviate from perfect one-dimensional performance. Reductions in the surface roughness of this fuel layer improve confidence in the ability of the ICF program to achieve ignition in the National Ignition Facility NIF, and increase the relevance of cryogenic experiments on the omega laser. We have developed a technique to generate a heat flux across this surface by applying an electric field to the DT vapor in the center of these shells. This vapor has a small but significant conductivity due to ionization caused by decay of tritium in the vapor and the solid. We describe here experiments using a 1.15 GHz cavity to apply an electric field to frozen DT inside of a sapphire test cell. The cell and cavity geometry allows visual observation of the frozen layers. We find that the resulting heat flux reduces the roughness of the icemore surface. less",
"title": "Smoothing of deuterium-tritium ice by electrical heating of the saturated vapor",
"URL": "http://ui.adsabs.harvard.edu/abs/1997PhRvE..55.3473M/abstract",
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"abstract": "For the past several years, the JET scientific programme Pamela et al 2007 Fusion Eng. Des. 82 590 has been engaged in a multi-campaign effort, including experiments in D, H and T, leading up to 2020 and the first experiments with 5050 DT mixtures since 1997 and the first ever DT plasmas with the ITER mix of plasma-facing component materials. For this purpose, a concerted physics and technology programme was launched with a view to prepare the DT campaign DTE2. This paper addresses the key elements developed by the JET programme directly contributing to the DT preparation. This intense preparation includes the review of the physics basis for the DT operational scenarios, including the fusion power predictions through first principle and integrated modelling, and the impact of isotopes in the operation and physics of DT plasmas thermal and particle transport, high confinement mode H-mode access, Be and W erosion, fuel recovery, etc. This effort also requires improving several aspects of plasma operation for DTE2, such as real time control schemes, heat load control, disruption avoidance and a mitigation system including the installation of a new shattered pellet injector, novel ion cyclotron resonance heating schemes such as the threeions scheme, new diagnostics neutron camera and spectrometer, active Alfven eigenmode antennas, neutral gauges, radiation hard imaging systems and the calibration of the JET neutron diagnostics at 14 MeV for accurate fusion power measurement. The active preparation of JET for the 2020 DT campaign provides an incomparable source of information and a basis for the future DT operation of ITER, and it is also foreseen that a large number of key physics issues will be addressed in support of burning plasmas.",
"title": "Overview of the JET preparation for deuterium–tritium operation with the ITER like-wall",
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"abstract": "Visible radioluminescence was observed from single 200μmdiam deuteriumtritium DTfilled glass microbubble laser targets. Most of the light is caused by tritium beta particles hitting the glass, and no beta particles escape outside the microbubble. At room temperature, white light is created with an efficiency of 0.2 to 0.3 photonsbeta particle. This efficiency rises an order of magnitude at 35 K, probably because of freezing of radiation defects into the glass. It decreases when the DT liquifies and drops even lower upon solidification. This is probably caused by pooling of the DT at the bottom of the microbubble plus light absorption in small crystallites. Radioluminescence offers a means of certifying the DT fill of individual microbubble laser targets made of transparent material.",
"title": "Radioluminescence of individual deuterium–tritium‐filled glass microbubble laser targets",
"URL": "http://scitation.aip.org/content/avs/journal/jvsta/5/5/10.1116/1.574271",
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"Radiation",
"Beta particle",
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"abstract": "Neutron-resonance transmission analysis NRTA is a powerful technique for materials identification with applications in many fields, but to date it has relied on major kilometer-long user facilities. Here the authors develop a methodology that significantly simplifies the necessary platform, allowing for laboratory implementations. Experiments demonstrate that the approach here can identify such elements as silver, indium, tungsten, and uranium. This success could turn NRTA, currently a niche technique, into an ubiquitous tool with applicability in nuclear engineering, archaeology, and arms control.",
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"abstract": "Fully kinetic, collisional, and electromagnetic simulations of the time evolution of an imploding and burning Z pinch plasma have been performed. Using the implicit particle-in-cell PIC code, multidimensional 1D and 3D simulations of deuterium and deuterium-tritium Z pinches provide insight into the mechanisms of neutron production. The PIC code allows non-Maxwellian particle distributions, simulates finite mean-free-path effects, performs self-consistent calculations of anomalous resistivity, and permits charge separation. At low pinch current, neutron production is dominated by high energy ions driven by instabilities. The instabilities produce a power-law ion-energy distribution function in the distribution tail. At higher currents with deuterium-tritium fuel, the vast majority of the neutrons is thermonuclear in origin and neutron yield follows an I4 neutron yield scaling with current. High-current, multidimension simulations up to 40 MA with 1016 neutron yield suggest that the fraction of the...",
"title": "Kinetic simulations of a deuterium-tritium Z pinch with >1016 neutron yielda)",
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"abstract": "Solid deuterium-tritium D-T fuel layers inside copper-doped beryllium shells are robust inertial confinement fusion fuel pellets. This paper describes the first characterization of such layers using phase-contrast -ray imaging. Good agreement is found between calculation and experimental contrast at the layer interfaces. Uniform solid D-T layers and their response to thermal asymmetries were measured in the BeCu shell. The solid D-T redistribution time constant was measured to be 28 min in the BeCu shell.",
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"sentence": "Good agreement is found between calculation and experimental contrast at the layer interfaces.",
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"sentence": "Uniform solid D-T layers and their response to thermal asymmetries were measured in the BeCu shell.",
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"abstract": "Reports the results obtained in a parametric investigation of the thermonuclear yield of deuterium-tritium pellets as a function of the initial laser power. The hydrodynamic equations used to describe the pellet-laser interaction and subsequent evolution include the following physical processes heat conduction with modifications due to the so-called free-streaming limit, energy exchange among the various particle species, ion viscosity, bremsstrahlung emission, classical absorption of laser power via inverse bremsstrahlung at densities below the critical density, rho and phenomenological anomalous absorption at densities rho rho , and thermonuclear reactions. Spherical symmetry is assumed.",
"title": "On the optimum laser power for maximum thermonuclear yield with deuterium-tritium pellets",
"URL": "https://ui.adsabs.harvard.edu/abs/1976PlPh...18..243C/abstract",
"fields_of_study": [
"Physics",
"Thermal conduction",
"Atomic physics",
"Laser power scaling",
"Pellets",
"Yield (chemistry)",
"Deuterium",
"Absorption (electromagnetic radiation)",
"Thermonuclear fusion",
"Bremsstrahlung"
],
"year_published": 1976,
"first_author": "S Cuperman",
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"abstract": "Within the framework of the shock-ignition SI scheme, ignition conditions are reached following the separation of the compression and heating phases. First, the shell is compressed at a sub-ignition implosion velocity then an intense laser spike is launched at the end of the main drive, leading to the propagation of a strong shock through the precompressed fuel. The minimal laser energy required for ignition of scaled deuteriumtritium DT targets is assessed by calculations. A semi-empiric model describing the ignitor shock generation and propagation in the fuel assembly is defined. The minimal power needed in the laser spike pulse to achieve ignition is derived from the hydrodynamic model. Optimal conditions for ignition of scaled targets are explored in terms of laser intensity, shell-implosion velocity, and target scale range for the SI process. Curves of minimal laser requirements for ignition are plotted in the energypower diagram. The most economic and reliable conditions for ignition of a millimeter DT target are observed in the 240- to 320-kms implosion velocity range and for the peak laser intensity ranging from 2 1015 Wcm2 up to 5 1015 Wcm2. These optimal conditions correspond to shock-ignited targets for a laser energy of 250 kJ and a laser power of 100 to 200 TW. Large, self-ignited targets are particularly attractive by offering ignition at a lower implosion velocity and a reduced laser intensity than for conventional ignition. The SI scheme allows for the compression and heating phases of the high power laser energy research facility target to be performed at a peak laser intensity below 1016 Wcm2. A better control of parametric and hydrodynamic instabilities within the SI scheme sets it as an optimal and reliable approach to attain ignition of large targets.",
"title": "Optimal conditions for shock ignition of scaled cryogenic deuterium–tritium targets",
"URL": "http://www.osti.gov/scitech/biblio/22113458",
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"Inertial confinement fusion",
"Nuclear engineering",
"Physics",
"Ignition system",
"Atomic physics",
"Implosion",
"Laser power scaling",
"IGNITOR",
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"Shock wave",
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"year_published": 2013,
"first_author": "M. Lafon",
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"abstract": "Single crystalDiamondDetectors SDD are being increasingly exploited for neutron diagnostics in high power fusion devices, given their significant radiation hardness and high energy resolution capabilities. The geometrical efficiency of SDDs is limited by the size of commercially available crystals, which is often smaller than the dimension of neutron beams along collimated lines of sight in tokamak devices. In this work, we present the design and fabrication of a 14 MeV neutron spectrometer consisting of 12 diamond pixels arranged in a matrix, so to achieve an improved geometrical efficiency. Each pixel is equipped with an independent high voltage supply and read-out electronics optimized to combine high energy resolution and fast signals 1 MHz spectroscopy. The response function of a prototype SDD to 14 MeV neutrons has been measured at the Frascati Neutron Generator by observation of the 8.3 MeV peak from the 12Cn, α9Be reaction occurring between neutrons and 12C nuclei in the detector. The measured energy resolution 2.5 FWHM meets the requirements for neutron spectroscopy applications in deuterium-tritium plasmas.",
"title": "A diamond based neutron spectrometer for diagnostics of deuterium-tritium fusion plasmas",
"URL": "https://aip.scitation.org/doi/10.1063/1.4885356",
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"Optics",
"Physics",
"Neutron",
"Neutron generator",
"Nuclear physics",
"Diamond",
"Neutron spectroscopy",
"Spectrometer",
"Bonner sphere",
"Deuterium",
"Neutron detection"
],
"year_published": 2014,
"first_author": "Carlo Cazzaniga",
"scholarly_citations_count": 45,
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"abstract": "Deuterium-tritium D-T neutron-induced radioactivity constitutes one of the foremost issues in fusion reactor design. Designers have been using radioactivity codes and associated nuclear data libraries for nucleonic designs offusion reactors. However, in the past, there was hardly any experimental validation of these codeslibraries. An elaborate, experimental program was initiated in 1988 under a U.S. Department of EnergyJapan Atomic Energy Research Institute collaborative program to validate the radioactivity codeslibraries. Measurements of decay gamma spectra from irradiated, high-purity samples of Al, Si, Ti, V, Cr, Mn-Cu alloy, Fe, Co, Ni, Cu, SS316AISI316, Zn, Zr, Nb, Mo, In, Sn, Ta, W, and Pb, among others, have been carried out under D-T neutron fluences ranging from 1.6 10 10 to 6.1 10 13 ncm 2 and cooling times ranging from 10 min to 3 weeks. As many as 14 neutron energy spectra were covered for a number of materials. The analyses of the isotopic activities of the irradiated materials using the activation cross-section libraries of four leading radioactivity codes, .., ACT4THIDA-2, REAC-3, DKR-ICF, and RACC, have shown large discrepancies among the calculations on one hand and between the calculations and the measurements, on the other. Vanadium, Co, Ni, Zn, Zr, Mo, In, Sn, and W each count the largest number of discrepant isotopic activities. It is strongly recommended to continue additional radioactivity experiments under additional neutron energy spectra and large neutron fluence on one hand and to improve activation cross sections related to the problematic isotopic activities on the other. A unique activation cross-section library and associated radioactivity code are also recommended for the best results. In addition to providing detailed results of the status of predictability of individual isotopic activities using the ACT4, REAC-3, DKR-ICF, and RACC activation cross-section libraries, safety factors cum quality factors characterizing each library are presented and discussed. The related issues of confidence level and associated uncertainty are also highlighted. These considerations are of direct practical importance to reactor designers.",
"title": "Decay Radioactivity Induced in Plasma-Facing Materials by Deuterium-Tritium Neutrons",
"URL": "https://www.tandfonline.com/doi/full/10.13182/FST95-A30403",
"fields_of_study": [
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"Radiochemistry",
"Nuclear physics",
"Materials science",
"Fusion power",
"Neutron temperature",
"Nuclear data",
"Deuterium",
"Tritium",
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"Neutron flux"
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"year_published": 1995,
"first_author": "Anil Kumar",
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"abstract": "AbstractThe reactivation process of a muon that is stuck to an alpha-particle produced in muon-catalyzed deuterium-tritium D-T fusion is studied for the different isotope targets , , and by using the Born approximation calculation of charge-transfer cross sections. The isotope dependence is small compared with the large isotope effects observed by Jones et al. Our calculated density dependence is very similar to that of Bracci and Fiorentini, and it is not as large as that observed by Jones et al. The enhancement of muon reactivation by application of a high-intensity electric field to the target is studied. Even when the very high electrical field of 40 MVcm is applied to a liquid-hydrogen target, the enhancement is small because of the isotropic emission of an alpha particle in unpolarized D-T fusion. Even in polarized D-T fusion, the enhancement is small.",
"title": "Reactivation Coefficient of Muon-Catalyzed Deuterium-Tritium Fusion and Its Enhancement",
"URL": "https://www.ans.org/pubs/journals/fst/a_24719",
"fields_of_study": [
"Isotope",
"Atomic physics",
"Materials science",
"Muon",
"Deuterium",
"Electric field",
"Tritium",
"Alpha particle",
"Kinetic isotope effect",
"Born approximation"
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"year_published": 1986,
"first_author": "Hiroshi Takahashi",
"scholarly_citations_count": 9,
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"abstract": "Experiments in the Tokamak Fusion Test Reactor TFTR have explored several novel regimes of improved tokamak confinement in deuterium-tritium D-T plasmas, including plasmas with reduced or reversed magnetic shear in the core and high-current plasmas with increased shear in the outer region high-. New techniques have also been developed to enhance the confinement in these regimes by modifying the plasma-limiter interaction through in-situ deposition of lithium. In reversed-shear plasmas, transitions to enhanced confinement have been observed at plasma currents up to 2.2 MA 4.3, accompanied by the formation of internal transport barriers, where large radial gradients develop in the temperature and density profiles. Experiments have been performed to elucidate the mechanism of the barrier formation and its relationship with the magnetic configuration and with the heating characteristics. The increased stability of high-current, high- plasmas produced by rapid expansion of the minor cross-section, coupled with improvement in the confinement by lithium deposition has enabled the achievement of high fusion power, up to 8.7 MW, with D-T neutral beam heating. The physics of fusion alpha-particle confinement has been investigated in these regimes, including the interactions of the alphas with endogenous plasma instabilities and externally applied waves in the ion cyclotron range of frequencies. In D-T plasmas with 1 and weak magnetic shear in the central region, a toroidal Alfven eigenmode instability driven purely by the alpha particles has been observed for the first time. The interactions of energetic ions with ion Bernstein waves produced by mode-conversion from fast waves in mixed-species plasmas have been studied as a possible mechanism for transferring the energy of the alphas to fuel ions.",
"title": "Deuterium–tritium plasmas in novel regimes in the Tokamak Fusion Test Reactor",
"URL": "https://ui.adsabs.harvard.edu/abs/1997PhPl....4.1714B/abstract",
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"Tokamak",
"Physics",
"Ion",
"Magnetic confinement fusion",
"Atomic physics",
"Instability",
"Fusion power",
"Tokamak Fusion Test Reactor",
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"year_published": 1997,
"first_author": "M.G. Bell",
"scholarly_citations_count": 30,
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"abstract": "The effect of high density shells on deuteriumtritium pellets imploded by laser energy deposition or other means is investigated. Attention is centered on the inner parts of the pellet where hydrodynamics is the dominant mechanism. The implosions can then be characterized by a pressure boundary condition. Numerical solutions of the implosions are carried out over a wide range of parameters both for solid pellets and pellets with a central void.",
"title": "Implosion characteristics of deuterium–tritium pellets surrounded by high density shells",
"URL": "https://ui.adsabs.harvard.edu/abs/1976PhFl...19.1495F/abstract",
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"Inertial confinement fusion",
"Physics",
"Composite material",
"Pellet",
"Nuclear physics",
"Implosion",
"Pellets",
"Laser",
"Deuterium",
"Plasma",
"Void (astronomy)"
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"abstract": "A review of experimental results obtained in JET D-T plasmas is presented. In discussing the underlying physics, results previously obtained on tokamak fusion test reactor TFTR are also taken into account. In JET, the maximum fusion power output of 16.1 MW has been obtained in an edge localized mode ELM-free hot-ion H-mode featuring an edge confinement barrier in a single-null divertor plasma with a where is the total input power to torus. A steady-state H-mode discharge, with plasma shape and safety factor similar to that of ITER, produced 4 MW for 5 22 MJ. The steady-state results extrapolate well to ignition with ITER parameters using the normalized plasma pressure achieved on JET. Also, the advanced tokamak regime using optimized magnetic shear configuration featuring an internal transport barrier produced 8.2 MW of fusion power. With regards to reactor physics issues, a clear identification of electron heating by fusion born-particles has been made both in JET and TFTR. The JET experiments show that the H-mode threshold power has approximately an inverse isotopic mass dependence and that it does not depend on the method of auxiliary heating. The global energy confinement time in the TFTR D-T supershot regime scales as but in the JET H-modes, it is found to be practically independent of isotopic mass where A is the atomic mass of the hydrogenic species. In JET, the plasma core and the edge appear to have different underlying confinement physics, the former follows the gyro-Bohm transport model whereas the edge pedestal energy scales as. The maximum edge pressure in H-modes is analysed in relation to the ion poloidal Larmor radius at the edge. The fast ions driven by neutral beam injections NBI or ion cyclotron resonance heating ICRH could play an important role in setting the width of the edge pedestal. The thermal ELMy H-mode confinement both in D or T gas fuelled plasmas decreases significantly when the plasma density exceeds 0.75 of the Greenwald limit and the maximum density achieved is. The ICRH scenarios for a reactor have been evaluated. For example, minority in 5050 DT and tritium-dominated plasmas showed strong bulk ion heating leading to ion temperatures up to 13 keV with ICRH alone. Deuterium-minority ion cyclotron heating in tritium plasmas at a power level of 6 MW produced steady-state record values of for more than 2.5 . Finally, the on-site closed-cycle tritium reprocessing plant and remote handling tools at JET have been used routinely and provided an integrated demonstration of safe and reliable operations of a tokamak device in reactor-relevant conditions.",
"title": "Deuterium-tritium operation in magnetic confinement experiments: results and underlying physics",
"URL": "https://iopscience.iop.org/article/10.1088/0741-3335/41/3A/002",
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"Jet (fluid)",
"Physics",
"Magnetic confinement fusion",
"Atomic physics",
"Nuclear physics",
"Fusion power",
"Divertor",
"Tokamak Fusion Test Reactor",
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"Edge-localized mode"
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"year_published": 1999,
"first_author": "J Jacquinot",
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"sentence": "Finally, the on-site closed-cycle tritium reprocessing plant and remote handling tools at JET have been used routinely and provided an integrated demonstration of safe and reliable operations of a tokamak device in reactor-relevant conditions.",
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"category": "Nuclear Fusion Experimental Facility",
"entity": "JET"
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"entity": "on-site closed-cycle tritium reprocessing plant"
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"category": "Chemical Element or Compound",
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}
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{
"abstract": "Deuterium tritium hybrid has been loaded on some LaNi 4.7 Al 0.3 samples and stored at room temprature for 480 and 1 120 days.The LaNi 4.7 Al 0.3 deuterotritide can retain nearly all the decay 3He. The tritium aging effects are observed by determining the equilibrium desorption isotherms for the deuterotritide.These effects include1 a decrease in the equilibrium plateau pressure2 an increase in the plateau slope3 a reduction in the reversible storage capacity4 the formation of tightly bound tritium or deuterium which is often referred as the hydrogen isotopic heel. It is found that heating to 623 K and vacuuming can reverse some of the tritium aging effects.",
"title": "AGING EFFECTS OF LaNi_(4.7)Al_(0.3) LOADED WITH DEUTERIUM TRITIUM",
"URL": "https://en.cnki.com.cn/Article_en/CJFDTOTAL-HXFS200201006.htm",
"fields_of_study": [
"Analytical chemistry",
"Desorption",
"Radiochemistry",
"Chemistry",
"Plateau pressure",
"Plateau (mathematics)",
"Helium-3",
"Hydrogen",
"Deuterium",
"Tritium"
],
"year_published": 2002,
"first_author": "Li Rong",
"scholarly_citations_count": "NaN",
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"sentence": "These effects include1 a decrease in the equilibrium plateau pressure2 an increase in the plateau slope3",
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"abstract": "Abstract Robust high performance plasma scenarios are being developed to exploit the unique capability of JET to operate with Tritium and Deuterium. In this context, real time control schemes are used to guide the plasma into the desired state and maintain it there. Other real time schemes detect undesirable behaviour and trigger appropriate actions to assure the best experimental results without unnecessary use of the limited neutron and Tritium budget. This paper discusses continuously active controllers and eventthreshold detection algorithms triggering a variety of actions. Recent advances include Control of the degree of plasma detachment via impurity injection ii ELM frequency control via gasPellet injection iii Sawtooth pacing using ICRH modulation, iv control of the Hydrogen to Deuterium isotope ratio through gas injection and the determination that a discharge is not evolving as desired, triggering a cascade of actions attempting to stop the plasma rapidly and safely, eventually triggering massive gas injection if a disruption is deemed unavoidable. For high power Deuterium-Tritium operation these control schemes need to be integrated into the plasma scenarios ensuring that they are mutually compatible.",
"title": "Real time control developments at JET in preparation for deuterium-tritium operation",
"URL": "https://iris.unibas.it/handle/11563/134558",
"fields_of_study": [
"Nuclear engineering",
"Real-time Control System",
"Jet (fluid)",
"Sawtooth wave",
"Power (physics)",
"Nuclear physics",
"Automatic frequency control",
"Context (language use)",
"Cascade",
"Computer science",
"Plasma"
],
"year_published": 2017,
"first_author": "M. Lennholm",
"scholarly_citations_count": 7,
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"sentence": "For high power Deuterium-Tritium operation these control schemes need to be integrated into the plasma scenarios ensuring that they are mutually compatible.",
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"abstract": "In the course of the Preliminary Tritium Experiment in JET, where combined deuterium and tritium neutral beam injection generated a DT fusion power of 1.7 MW, ion cyclotron emission ICE was measured in the frequency range 180 MHz. The ICE spectra contain superthermal, narrow, equally spaced emission lines, which correspond to successive cyclotron harmonics of deuterons or alpha particles at the outer midplane, close to tile last closed flux surface at major radius R approximately 4.0 . Above about 100 MHz the lines merge into a relatively intense continuum. The ICE signal fluctuates rapidly in time, and is extinguished whenever a large amplitude edge localized mode ELM occurs. In pure deuterium and mixed DT discharges ICE spectra are similar in form, but on changing from pure D to mixed DT neutral beam injection at constant power, the intensity of the ICE rises in proportion to the increased neutron flux this indicates that fusion alpha particles-and not beam ions-provide the free energy to generate ICE. The JET ICE database, which now extends over a range of six decades in signal intensity, shows that the time averaged ICE power increases almost linearly with total neutron flux. The rise and fall of the neutron flux during a single discharge is closely followed by that of the ICE signal, which is delayed by a time of the order of the fusion product slowing down time. This feature is well modelled by a TRANSP code simulation of the density of deeply trapped fusion products reaching the plasma edge. Calculations reveal a class of fusion products, born in the core, which make orbital excursions of sufficient size to reach the outer midplane edge. There, the velocity distribution has a ring structure, which is found to be linearly unstable to relaxation to obliquely propagating waves on the fast Alfven-ion Bernstein branch at all ion cyclotron harmonics. The paper shows how ICE provides a unique diagnostic for fusion alpha particles",
"title": "Ion cyclotron emission measurements during JET deuterium-tritium experiments",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/33/9/I10",
"fields_of_study": [
"Physics",
"Atomic physics",
"Fusion power",
"Neutral beam injection",
"Edge-localized mode",
"Cyclotron",
"Deuterium",
"Alpha particle",
"Neutron flux",
"Emission spectrum"
],
"year_published": 1993,
"first_author": "G.A. Cottrell",
"scholarly_citations_count": 133,
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"sentence": "The JET ICE database, which now extends over a range of six decades in signal intensity, shows that the time averaged ICE power increases almost linearly with total neutron flux.",
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"category": "Physical Process",
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"abstract": "Measurements of the Dd,pT dd and Tt,2n4He tt reaction yields have been compared with those of the Dt,n4He dt reaction yield, using deuterium-tritium gas-filled inertial confinement fusion capsule implosions. In these experiments, carried out on the OMEGA laser, absolute spectral measurements of dd protons and tt neutrons were obtained. From these measurements, it was concluded that the dd yield is anomalously low and the tt yield is anomalously high relative to the dt yield, an observation that we conjecture to be caused by a stratification of the fuel in the implosion core. This effect may be present in ignition experiments planned on the National Ignition Facility.",
"title": "Evidence for stratification of deuterium-tritium fuel in inertial confinement fusion implosions.",
"URL": "http://ui.adsabs.harvard.edu/abs/2012PhRvL.108g5002C/abstract",
"fields_of_study": [
"Inertial confinement fusion",
"Neutron",
"Lawson criterion",
"Nuclear physics",
"Materials science",
"Implosion",
"National Ignition Facility",
"Yield (chemistry)",
"Deuterium",
"Tritium"
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"year_published": 2012,
"first_author": "D. T. Casey",
"scholarly_citations_count": 62,
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"abstract": "Describes a series of experiments in the Joint European Torus JET, culminating in the first tokamak discharges in deuterium-tritium fuelled mixture. The experiments were undertaken within limits imposed by restrictions on vessel activation and tritium usage. The objectives were to produce more than one megawatt of fusion power in a controlled way ii to validate transport codes and provide a basis for accurately predicting the performance of deuterium-tritium plasmas from measurements made in deuterium plasmas iii to determine tritium retention in the torus systems and to establish the effectiveness of discharge cleaning techniques for tritium removal iv to demonstrate the technology related to tritium usage and to establish safe procedures for handling tritium in compliance with the regulatory requirements. A single-null X-point magnetic configuration, diverted onto the upper carbon target, with reversed toroidal magnetic field was chosen. Deuterium plasmas were heated by high power, long duration deuterium neutral beams from fourteen sources and fuelled also by up to two neutral beam sources injecting tritium. The results from three of these high performance hot ion H-mode discharges are described a high performance pure deuterium discharge a deuterium-tritium discharge with a 1 mixture of tritium fed to one neutral beam source and a deuterium-tritium discharge with 100 tritium fed to two neutral beam sources. The TRANSP code was used to check the internal consistency of the measured data and to determine the origin of the measured neutron fluxes. In the best deuterium-tritium discharge, the tritium concentration was about 11 at the time of peak performance, when the total neutron emission rate was 6.0 1017 neutronss. The integrated total neutron yield over the high power phase, which lasted about 2 , was 7.2 1017 neutrons, with an accuracy of 7. The actual fusion amplification factor, QDT was about 0.15",
"title": "Fusion energy-production from a deuterium-tritium plasma in the jet tokamak",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/32/2/I01",
"fields_of_study": [
"Tokamak",
"Neutron",
"Lawson criterion",
"Neutron generator",
"Nuclear physics",
"Materials science",
"Fusion power",
"Joint European Torus",
"Deuterium",
"Tritium"
],
"year_published": 1992,
"first_author": "Jet Team",
"scholarly_citations_count": 349,
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"abstract": "The fusion-born alpha particle heating in magnetically confined fusion machines is a high priority subject for studies. The self-heating of thermonuclear fusion plasma by alpha particles was observed in recent deuterium-tritium D-T experiments on the joint European torus. This observation was possible by conducting so-called afterglow experiments where transient high fusion yield was achieved with neutral beam injection as the only external heating source, and then termination of the heating at peak performance. This allowed the first direct evidence for electron heating of plasmas by fusion-born alphas to be obtained. Interpretive transport modeling of the relevant D-T and reference deuterium discharges is consistent with the alpha particle heating observation.",
"title": "Evidence of Electron Heating by Alpha Particles in JET Deuterium-Tritium Plasmas.",
"URL": "http://link.aps.org/pdf/10.1103/PhysRevLett.131.075101",
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"Thermonuclear fusion",
"Deuterium",
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"Tritium",
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"abstract": "We have previously demonstrated, based upon a onedimensional analysis, that beta heating could cause a redistribution of nonuniform deuteriumtritium DT ice within a cryogenic target at an ideal rate that would decrease nonuniformity by a factor of 10 every hour. Our analysis was extended to address two pertinent questions for a spherical target, where will the DT ice finally go and how quickly will it get there This analysis is a twodimensional heat and mass transfer problem. We have used PLTMG, a stateoftheart multigrid computer code for the analysis. For the tent mount method of positioning a target in a cryogenic enclosure, an ice layer nonuniformity of 1 can be achieved. We have evaluated the rate of ice redistribution and report its variation as a function of 3He content within the target, the target temperature, target geometry, and thermal conductivity of the shell wall.",
"title": "Beta heating driven deuterium-tritium ice redistribution, modeling studies",
"URL": "http://ui.adsabs.harvard.edu/abs/1989JVSTA...7.1157M/abstract",
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"Cryogenics",
"Atomic physics",
"Chemistry",
"Radioactive decay",
"Charged particle",
"Mass transfer",
"Mechanics",
"Deuterium",
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"abstract": "This paper reports the first deuteriumtritium D-T fusion experiments in the geometry of the International Thermonuclear Experimental Reactor ITER, with long pulse length and an ITER-like divertor. Physics aspects, such as the isotope dependence of confinement, the H-mode high confinement threshold, shear optimisation, heating methods, high fusion performance and alpha particle heating, are discussed together with their implications. The technology aspects of tritium wall loading and clean-up, the close coupled tritium plant and the future remote handling divertor target exchange are also mentioned.",
"title": "Deuterium-tritium plasmas in the Joint European Torus (JET): Behavior and implications",
"URL": "https://infoscience.epfl.ch/record/119633",
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"Magnetic confinement fusion",
"Nuclear physics",
"Fusion power",
"Joint European Torus",
"Divertor",
"Deuterium",
"Tritium",
"Thermonuclear fusion",
"Plasma"
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"first_author": "A. Gibson",
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"abstract": "A detailed numerical study has been made, using a Monte-Carlo neutron-transport method, of the total heating and heating distribution functions due to thermonuclear neutrons in laser-compressed deuterium-tritium spheres. A series of formulae is presented which will allow this heating to be rapidly and accurately computed in computer-modelling studies of laser fusion.",
"title": "A study of fusion-neutron heating in laser-compressed deuterium-tritium spheres",
"URL": "https://iopscience.iop.org/article/10.1088/0305-4616/3/1/010",
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"Physics",
"Neutron",
"Nuclear physics",
"Distribution function",
"Laser",
"Deuterium",
"Tritium",
"Thermonuclear fusion",
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"first_author": "T D Beynon",
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"abstract": "We investigate the deuterium-tritium DT fusion process in the presence of strong laser fields with a semiclassical SC method. In this model, two nuclei with a given incident kinetic energy that closely approach each other are simulated by tracing the classical Newtonian trajectories in the combined Coulomb repulsive potentials and laser fields. At the nearest position or classical turning point, quantum tunneling through the Coulomb barrier emerges, and its penetrability is estimated with the Wentzel-Kramers-Brillouin formula. Nuclear fusion occurs after the tunneling, and the total fusion cross section takes the Gamow form. We find that the tunneling penetrability can be enhanced dramatically because the nuclei can closely approach each other due to the quiver motion of the charged nuclei driven by the intense laser fields. We then calculate the DT fusion section for a wide range of laser parameters according to various incident nuclei kinetic energies and obtain the phase diagrams for the enhanced DT fusion. We compare our SC results with the quantum results of the Kramers-Henneberger approximation and the Volkov state approximation.",
"title": "Deuterium-tritium fusion process in strong laser fields: Semiclassical simulation",
"URL": "https://link.aps.org/doi/10.1103/PhysRevC.104.044614",
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"Quantum tunnelling",
"Physics",
"Kinetic energy",
"Fusion",
"Atomic physics",
"Laser",
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"abstract": "This paper reports that high-magnetic-field, toroidal deuterium-tritium plasmas can have a window of accessibility to lower hybrid radio-frequency at moderate frequency. As an example, lower hybrid waves at 8 GHz are shown to penetrate most of the way into subignited and ignited Ignitor plasmas at full density and magnetic field, using a one-dimensional transport and ray-tracing code. Better heating of the plasma interior is obtained by launching from a negative poloidal angle relative to the horizontal midplane.",
"title": "Lower hybrid heating in a high-field deuterium-tritium ignition experiment",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST92-A30106",
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"IGNITOR",
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"abstract": "In this paper, the method of the operation path on the generalized ignition contour map, , T is used to treat the ignition accessibility of a deuterium-tritium tokamak reactor for different types of confinement scaling including offset linear scaling. It is shown that the operation paths and ignition boundary on the-T plane as well as the -T plane provide a useful ignition criterion for various types of scaling. The International Thermonuclear Experiment Reactor ITER tokamaks with low and high toroidal fields are used as examples.",
"title": "Operation Path Method for Ignition Criterion in a Deuterium-Tritium Tokamak Reactor",
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"abstract": "The thermonuclear burn-up in deuterium-tritium DT mixtures with various D T ratios is considered. It is shown that the use of small amounts of tritium simplifies the thermonuclear burn-up in the dense deuterium significantly. The general dependence of the critical burn-up parameter xc D rc upon the D T ratio, temperature T and initial density 0 is studied. In particular, we found that when the D T ratio decreases the critical burn-up parameter xc.T 0 diminishes very quickly at fixed T and 0, .. the thermonuclear burn-up simplifies when the relative tritium concentration in the DT-mixture grows. The thermonuclear burn-up in the highly compressed deuterides and DT-hydrides of light elements is discussed briefly in the appendix.",
"title": "The thermonuclear burn-up in deuterium - tritium mixtures and hydrides of light elements",
"URL": "https://www.researchgate.net/profile/Alexei_Frolov/publication/231095277_The_thermonuclear_burn-up_in_deuterium_-_tritium_mixtures_and_hydrides_of_light_elements/links/546fdd0b0cf216f8cfa9e728.pdf",
"fields_of_study": [
"Nuclear physics",
"Materials science",
"Burnup",
"Concentration ratio",
"Deuterium",
"Tritium",
"Thermonuclear fusion"
],
"year_published": 1998,
"first_author": "Alexei M. Frolov",
"scholarly_citations_count": 12,
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"sentence": "The thermonuclear burn-up in the highly compressed deuterides and DT-hydrides of light elements is discussed briefly in the appendix.",
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"abstract": "The development of next-step neutron spectrometers for use on high-power especially burning fusion plasmas is described. The expected performance specifications of optimized designs are compared with the fundamental limits of neutron diagnostics set by the underlying nuclear reactions for neutron detection. The potential results of the next-step spectrometers on the International Thermonuclear Experimental Reactor ITER and the Joint European Torus JET are illustrated, especially those derivable from details in the single-component neutron spectrum of thermal ion reactions and from the separation of thermal and supra-thermal ion reactions in multiple-component spectra. The information content and its relationship to the quality of neutron spectrometry data are illustrated, and some implications on alpha-particle issues are discussed. 16 refs., 8 figs.",
"title": "Neutron observations and alpha particles in high-power deuterium-tritium plasmas",
"URL": "https://ans.org/pubs/journals/fst/a_30291",
"fields_of_study": [
"Neutron scattering",
"Physics",
"Neutron",
"Neutron source",
"Nuclear physics",
"Fusion power",
"Neutron temperature",
"Joint European Torus",
"Thermonuclear fusion",
"Neutron detection"
],
"year_published": 1994,
"first_author": "Jan Källne",
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"abstract": "The deuteriumtritium DT fusion reaction, DT,γ5He, has a rare 4.2 105 branching ratio that releases a 16 MeV gamma ray instead of the more common 14.1 MeV fusion neutron. These fusion gamma rays can be used as a complementary source of measuring the net fusion yield of experiments. Fusion gamma rays have the advantage of having negligible Doppler broadening, being isotropic and less down-scattered compared to fusion neutrons. At the National Ignition Facility, the DT fusion gamma rays are measured by the Gamma Reaction History diagnostic that thresholds to only measure 10 MeV gamma rays. After removing a 12 contribution from neutron capture interactions in deuterium, Dn,γT, and carbon, 12Cn,γ13C, the deviation between GRH measurements and neutron-based yield measurements has been reduced to 10. Further improvements are needed for detailed physics comparison.",
"title": "Total fusion yield measurements using deuterium–tritium gamma rays",
"URL": "https://aip.scitation.org/doi/10.1063/5.0055846",
"fields_of_study": [
"Physics",
"Neutron",
"Radiochemistry",
"National Ignition Facility",
"Neutron capture",
"Deuterium",
"Doppler broadening",
"Tritium",
"Nuclear fusion",
"Gamma ray"
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"year_published": 2021,
"first_author": "K. D. Meaney",
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"abstract": "After many years of fusion research, the conditions needed for a DT fusion reactor have been approached on the Tokamak Fusion Test Reactor TFTR. For the first time the unique phenomena present in a DT plasma are now being studied in a laboratory plasma.The first magnetic fusion experiments to study plasmas using nearly equal concentrations of deuterium and tritium have been carried out on TFTR. At present the maximum fusion power of 10.7 MW, using 39.5 MW of neutralbeam heating, in a supershot discharge and 6.7 MW in a highβp discharge following a current rampdown. The fusion power density in a core of the plasma is 2.8 MW m3, exceeding that expected in the International Thermonuclear Experimental Reactor ITER at 1500 MW total fusion power. The energy confinement time, τE, is observed to increase in DT, relative to D plasmas, by 20 and the ni0 Ti0 τE product by 55. The improvement in thermal confinement is caused primarily by a decrease in ion heat conductivity in both supershot and limiterHmode discharges. Extensive lithium pellet injection increased the confinement time to 0.27 and enabled higher current operation in both supershot and highβp discharges. Ion cyclotron range of frequencies ICRF heating of a DT plasma, using the second harmonic of tritium, has been demonstrated. First measurements of the confined alpha particles have been performed and found to be in good agreement with TRANSP simulations. Initial measurements of the alpha ash profile have been compared with simulations using particle transport coefficients from He gas puffing experiments. The loss of alpha particles to a detector at the bottom of the vessel is well described by the firstorbit loss mechanism. No loss due to alphaparticledriven instabilities has yet been observed. DT experiments on TFTR will continue to explore the assumptions of the ITER design and to examine some of the physics issues associated with an advanced tokamak reactor.",
"title": "Review of deuterium-tritium results from the Tokamak Fusion Test Reactor",
"URL": "http://www.osti.gov/scitech/biblio/64021",
"fields_of_study": [
"Inertial confinement fusion",
"Tokamak",
"Physics",
"Magnetic confinement fusion",
"Lawson criterion",
"Nuclear physics",
"Fusion power",
"Tokamak Fusion Test Reactor",
"Nuclear fusion",
"Thermonuclear fusion"
],
"year_published": 1995,
"first_author": "K. M. McGuire",
"scholarly_citations_count": 90,
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"sentence": "Initial measurements of the alpha ash profile have been compared with simulations using particle transport coefficients from He gas puffing experiments.",
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{
"abstract": "The energy distribution of neutrons, from the source energy of 14 MeV down to the ,2n threshold, can be approximated by effective one-group cross sections for such high and medium mass number el...",
"title": "Analysis of the Amplification of Deuterium-Tritium Neutron Sources: Part 2-Application",
"URL": "http://www.ans.org/pubs/journals/nse/a_27438",
"fields_of_study": [
"Neutron",
"Neutron source",
"Nuclear physics",
"Energy (signal processing)",
"Materials science",
"Energy distribution",
"Deuterium",
"Tritium",
"Mass number"
],
"year_published": 1985,
"first_author": "M. Segev",
"scholarly_citations_count": 2,
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{
"abstract": "Thermonuclear reaction rate describing thermonuclear burning efficiency in thermonuclear fusion is studied.As one species atomic nucleus with Maxwell velocity distribution,another species atomic nucleus velocity is divided into several groups.Velocity group thermonuclear reaction rate and averaged thermonuclear reaction rate are deduced,and simulation codes are obtained.Taking deuterium-tritium thermonuclear fusion reaction as an example,velocity group thermonuclear reaction rates and corresponding averaged thermonuclear reaction rates are calculated and analyzed comparing with exact direct integration results.Finally,relation between averaged thermonuclear reaction rate and velocity group number is studied.",
"title": "Simulation and Analysis of Deuterium-Tritium Thermonuclear Reaction Rate in Velocity Groups",
"URL": "http://en.cnki.com.cn/Article_en/CJFDTOTAL-JSWL201303010.htm",
"fields_of_study": [
"Physics",
"Atomic nucleus",
"Atomic physics",
"Nuclear physics",
"Maxwell–Boltzmann distribution",
"Thermonuclear reaction",
"Deuterium",
"Tritium",
"Thermonuclear fusion"
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"year_published": 2013,
"first_author": "Jia Hongxiang",
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"abstract": "There is a known demand for a fusion prototypic neutron source capable of emulating the neutron-induced damage caused by fusion. If no such source is developed in a timely and economical manner, the use of fusion as a source of energy will be hindered by material selection and qualification. Presented here is one possible path toward the development of a fusion prototypic neutron source by enhancing an operational neutron generator platform with so-called plasma windows. The use of plasma windows addresses a weakness in the current design by improving the pressure differential between acceleration and the target regions. This improvement, combined with the use of multiple beamlines, represents the possibility of dramatically increasing the fusion neutron flux capabilities of such a system.",
"title": "A Plasma Window–Enhanced Accelerator-Based Deuterium-Tritium Neutron Generator System",
"URL": "NaN",
"fields_of_study": [
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"Neutron source",
"Neutron",
"Nuclear engineering",
"Fusion power",
"Plasma",
"Neutron flux",
"Tritium",
"Fusion",
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"Acceleration",
"Tokamak",
"Physics",
"Computer science",
"Materials science",
"Engineering",
"Linguistics",
"Philosophy",
"Classical mechanics"
],
"year_published": 2023,
"first_author": "J. M. Blatz",
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"sentence": "If no such source is developed in a timely and economical manner, the use of fusion as a source of energy will be hindered by material selection and qualification.",
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"sentence": "Presented here is one possible path toward the development of a fusion prototypic neutron source by enhancing an operational neutron generator platform with so-called plasma windows.",
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"sentence": "This improvement, combined with the use of multiple beamlines, represents the possibility of dramatically increasing the fusion neutron flux capabilities of such a system.",
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"abstract": "We propose and we justify a Monte-Carlo algorithm which solves a spatially homogeneous kinetic equation of Boltzmann type that models the fusion reaction between a deuterium ion and a tritium ion, and giving an particle and a neutron. The proposed algorithm is validated with the use of explicit solutions of the kinetic model obtained by replacing the fusion cross-section by a Maxwellian cross section. R esum . On propose et on justie un algorithme de type Monte-Carlo permettant de esoudre un mod ele cin etique homog ene en espace de type Boltzmann mod elisant la eaction de fusion entre un ion deut erium et un ion tritium, et donnant une particule et un neutron. Lalgorithme propos est par ailleurs valid via des solutions explicites du mod ele cin etique obtenues en rempla cant la section ecace de fusion par une section ecace maxwellienne.",
"title": "Numerical simulation by a random particle method of Deuterium-Tritium fusion reactions in a plasma.",
"URL": "https://www.esaim-proc.org/articles/proc/abs/2012/04/proc123812/proc123812.html",
"fields_of_study": [
"Physics",
"Statistical physics",
"Ion",
"Neutron",
"Fusion",
"Atomic physics",
"Boltzmann constant",
"Deuterium",
"Tritium",
"Nuclear fusion",
"Plasma"
],
"year_published": 2012,
"first_author": "Frédérique Charles",
"scholarly_citations_count": 2,
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"abstract": "The possibility of using small initial charges of tritium and sup 3He to boost a deuterium field-reversed configuration FRC up to temperatures at which deuterium-deuterium D-D ignition can take place is examined. A computer program is used to track the rates of production, reaction, and leakage of the FRC plasmas isotopic constituents as the burn progresses and the FRCs temperature, density, and volume vary. On the basis of these studies and current scaling laws, a highly attractive advanced fuel FRC reactor is outlined. It is cylindrical, 12 long, and 3.2 in coil outer radius, and produces 1568 MWelectric, giving it an effective core powervolume ratio as great as a pressurized water reactor. No lithium blanket is required, as the tritium needed for startup can be bred by the D-D reactions themselves.",
"title": "A deuterium-tritium ignition ramp for an advanced fuel field-reversed configuration reactor",
"URL": "http://www.osti.gov/scitech/biblio/6138023-deuterium-tritium-ignition-ramp-advanced-fuel-field-reversed-configuration-reactor",
"fields_of_study": [
"Nuclear engineering",
"Surface-area-to-volume ratio",
"Ignition system",
"Field-reversed configuration",
"Nuclear physics",
"Materials science",
"Blanket",
"Pressurized water reactor",
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"Deuterium",
"Tritium"
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"year_published": 1986,
"first_author": "Robert M. Zubrin",
"scholarly_citations_count": 1,
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"abstract": "Abstract The Joint European Torus recently carried out an experimental campaign using a plasma consisting of both deuterium D and tritium T. We observed a high-frequency mode using a reflectometer and an interferometer in a D-T plasma heated with low power neutral beam injection, P N B I 11.6 MW. This mode was observed at a frequency 156 kHz and was located at major radii 3.1 R 3.3. The observed mode was identified as a toroidal Alfvén eigenmode TAE using the linear MHD code, MISHKA. Beam ions and fusion-born alpha particles were modelled using the full orbit particle tracking code LOCUST, which produces smooth distribution functions suitable for stability calculations without analytical fits or the use of moments. We calculated the stability of the 21 candidate modes using the HALO code. These calculations revealed that beam ions can drive TAEs with toroidal mode numbers 8 with linear growth rates γ ω 1, while TAEs with lt 8 are damped by the beam ion population. Alpha particles drive modes with significantly smaller linear growth rates, γ α ω 0.1 due to the low alpha power generated almost exclusively by beam-thermal fusion reactions. Non-ideal effects were calculated using complex resistivity in the CASTOR code, leading to an assessment of radiative, collisional, and continuum damping for all 21 candidate modes. Ion Landau damping was modelled using Maxwellian distribution functions for bulk D and T ions in HALO. Radiative damping, the dominant bulk damping mechanism, suppresses modes with high toroidal mode numbers. Comparing the drive from energetic particles with damping from thermal particles, we find all but one of the candidate modes are damped. The single net-driven 9 TAE with a net growth rate γ ω 0.02 matches experimental observations with a lab frequency 163 kHz and location R 3.3 . The TAE was driven by co-passing particles through the A 5 resonance. Both co- and counter-passing alpha particles drive the TAE through the A 3 resonance. Additional sideband resonances contribute significant drive for both beam and alpha particles.",
"title": "Toroidal Alfvén eigenmodes observed in low power JET deuterium–tritium plasmas",
"URL": "https://iopscience.iop.org/article/10.1088/1741-4326/acedc3/pdf",
"fields_of_study": [
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"Materials science",
"Algorithm",
"Physics",
"Plasma",
"Computer science",
"Nuclear physics",
"Tokamak"
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"year_published": 2023,
"first_author": "H.J.C. Oliver",
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"abstract": "More than two dozen inertial confinement fusion ignition experiments with cryogenic deuterium-tritium layers have now been performed on the National Ignition Facility NIF. Each of these yields a wealth of data including neutron yield, neutron down-scatter fraction, burn-averaged ion temperature, -ray image shape and size, primary and down-scattered neutron image shape and size, etc. Compared to 2-D radiation-hydrodynamics simulations modeling both the hohlraum and the capsule implosion, however, the measured capsule yield is usually lower by a factor of 5 to 10, and the ion temperature varies from simulations, while most other observables are well matched between experiment and simulation. In an effort to understand this discrepancy, we perform detailed post-shot simulations of a subset of NIF implosion experiments. Using two-dimensional HYDRA simulations of the capsule only, these simulations represent as accurately as possible the conditions of a given experiment, including the as-shot capsule metrology, capsule surface roughness, and ice layer defects as seeds for the growth of hydrodynamic instabilities. The radiation drive used in these capsule-only simulations can be tuned to reproduce quite well the measured implosion timing, kinematics, and low-mode asymmetry. In order to simulate the experiments as accurately as possible, a limited number of fully three-dimensional implosion simulations are also being performed. Despite detailed efforts to incorporate all of the effects known and believed to be important in determining implosion performance, substantial yield discrepancies remain between experiment and simulation. Some possible alternate scenarios and effects that could resolve this discrepancy are discussed.",
"title": "Detailed implosion modeling of deuterium-tritium layered experiments on the National Ignition Facilitya)",
"URL": "https://scitation.aip.org/content/aip/journal/pop/20/5/10.1063/1.4802194",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Neutron",
"Ignition system",
"Nuclear physics",
"Implosion",
"Electron temperature",
"National Ignition Facility",
"Computational physics",
"Plasma diagnostics",
"Hohlraum"
],
"year_published": 2013,
"first_author": "Daniel Clark",
"scholarly_citations_count": 131,
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"sentence": "In order to simulate the experiments as accurately as possible, a limited number of fully three-dimensional implosion simulations are also being performed.",
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"sentence": "Despite detailed efforts to incorporate all of the effects known and believed to be important in determining implosion performance, substantial yield discrepancies remain between experiment and simulation.",
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"abstract": "Conditions for thermonuclear burn-up of an equimolar mixture of deuterium-tritium in non-equilibrium plasma have been investigated by four temperature theory. The photon distribution shape significantly affects the nature of thermonuclear burn. In three temperature model, the photon distribution is Planckian but in four temperature theory the photon distribution has a pure Planck form below a certain cut-off energy and then for photon energy above this cut-off energy makes a transition to Bose-Einstein distribution with a finite chemical potential. The objective was to develop four temperature theory in a plasma to calculate the critical burn up parameter which depends upon initial density, the plasma components initial temperatures, and hot spot size. All the obtained results from four temperature theory model are compared with 3 temperature model. It is shown that the values of critical burn-up parameter calculated by four temperature theory are smaller than those of three temperature model.",
"title": "Determination of deuterium–tritium critical burn-up parameter by four temperature theory",
"URL": "https://aip.scitation.org/doi/full/10.1063/1.4938274",
"fields_of_study": [
"Physics",
"Photon",
"Atomic physics",
"Photon energy",
"Distribution (number theory)",
"Bose–Einstein condensate",
"Deuterium",
"Bose–Einstein statistics",
"Thermonuclear fusion",
"Plasma"
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"year_published": 2015,
"first_author": "M. Nazirzadeh",
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"abstract": "AbstractDeuterium-deuterium and deuterium-tritium reaction rates may be compared to determine plasma temperatures in the 10- to 200-eV range. Distinguishing neutrons from these two reactions is difficult when yields are low or unpredictable. Time-of-flight TOF methods fail if the source is extended in time. These neutrons may be distinguished because inelastic scattering of more energetic neutrons by carbon produces a 4.44-MeV gamma ray and because hydrogenous material preferentially attenuates lower-energy neutrons. We describe a detector system that can discriminate between lower- and higher-energy neutrons for fluences as low as O102 neutrons per sterad even when TOF methods fail, define a figure of merit, and calculate its performance over a broad range of parameters.",
"title": "Plasma Temperature Inference from Deuterium-Tritium/Deuterium-Deuterium Neutron Discrimination",
"URL": "https://www.ans.org/pubs/journals/nse/a_36936",
"fields_of_study": [
"Figure of merit",
"Inelastic scattering",
"Neutron",
"Nuclear physics",
"Materials science",
"Range (particle radiation)",
"Deuterium",
"Tritium",
"Gamma ray",
"Plasma"
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"sentence": "These neutrons may be distinguished because inelastic scattering of more energetic neutrons by carbon produces a 4.44-MeV gamma ray and because hydrogenous material preferentially attenuates lower-energy neutrons.",
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"abstract": "A 14 MeV neutron spectrometer, based on the principle of the proton recoil telescope, has been installed as a deuteriumtritium DT plasma diagnostic at the Joint European Torus. The device comprises three identical telescope modules arranged one behind the other, to increase efficiency without worsening resolution. It views the plasma along a horizontal line of sight. The total efficiency is 7.05105 counts per neutron per cm2, and the calculated response function has a full width at half maximum of 2.2 at an incident neutron energy of 14.1 MeV. The spectrometer was operational throughout the recent DT experiment No. 1, and selected neutron spectra have been analyzed in terms of the contributions from the various neutron production mechanisms.",
"title": "A 14 MeV neutron spectrometer for the Joint European Torus deuterium-tritium experiments",
"URL": "https://aip.scitation.org/doi/10.1063/1.1149296",
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"Physics",
"Neutron",
"Nuclear physics",
"Neutron temperature",
"Joint European Torus",
"Neutron spectroscopy",
"Telescope",
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"Bonner sphere",
"Deuterium"
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"year_published": 1999,
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"abstract": "The toroidicity-induced Alfven eigenmodes TAE are found to be stable in the Tokamak Fusion Test Reactor TFTR deuterium-tritium plasmas. The dominant stabilizing mechanisms are beam ion Landau damping and radiative damping. A core localized TAE mode is shown to exist near the center of the plasma at small magnetic shear and finite plasma beta, which can be destabilized by energetic alpha particles in future TFTR DT experiments. With additional instability drive from fast minority ions powered by ion cyclotron radio frequency, both the global and core localized TAE modes can be readily destabilized.",
"title": "Stability analysis of toroidicity-induced Alfvén eigenmodes in TFTR deuterium-tritium experiments.",
"URL": "http://ui.adsabs.harvard.edu/abs/1995PhRvL..75.2336F/abstract",
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"Physics",
"Ion",
"Atomic physics",
"Instability",
"Tokamak Fusion Test Reactor",
"Beta (plasma physics)",
"Cyclotron",
"Alpha particle",
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"year_published": 1995,
"first_author": "Guoyong Fu",
"scholarly_citations_count": 53,
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{
"abstract": "Experiments to heat D- T plasmas with ion cyclotron range of frequency ICRF waves have been conducted for the first time on the tokamak fusion test reactor TFTR Wilson et al 1995 Phys. Rev. Lett. 75 842. Experiments were performed with full-bore discharges in the low recycling, neutral-beam-heated supershot Strachan et al 1987 Phys. Rev. Lett. 58 1004 regime with global energy confinement times exceeding twice the empirical L-mode value. Up to 5.9 MW of 43 MHz ICRF power was coupled into plasmas fuelled and heated by 18- 24 MW of 100 keV D- T neutral beam injection. The fraction of neutral beam power in tritium was varied from 14 to 100 and the toroidal magnetic field was scanned to move the second harmonic tritium layer across the plasma magnetic axis. With the layer on axis, the central ion temperature was increased from approximately 25 to 33 keV when 5.5 MW of ICRF power was added to a plasma fuelled and heated by 13.5 MW of T and 10 MW of D neutral beam injection. Up to 60 of the ICRF power was absorbed via ion heating within the core of a plasma with reactor-relevant parameters. Amplitude-modulated ICRF power was used to measure RF power absorption directly. The results were consistent with models used to predict the performance of ICRF heating scenarios in future machines, such as the international thermonuclear experimental reactor ITER. Despite extensive plasma conditioning, assisted by neutral beam heating and lithium pellet injection, many discharges were characterized by a degradation in performance and reactivity early in the neutral beam pulse. The degradation resulted from enhanced recycling of impurities and deuterium from the carbon tile limiters. The proximity of the outboard limiter exacerbated attempts to limit this enhanced influx.",
"title": "ICRF heating of TFTR plasmas fuelled by deuterium - tritium neutral beam injection",
"URL": "http://ui.adsabs.harvard.edu/abs/1996PPCF...38..723T/abstract",
"fields_of_study": [
"Beam (structure)",
"Atomic physics",
"Materials science",
"Neutral beam injection",
"Tokamak Fusion Test Reactor",
"Cyclotron",
"Limiter",
"Deuterium",
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{
"abstract": "The transport equation of Antal and Lee has been solved analytically to obtain the energy flux of α particles in a fully ionized deuteriumtritium plasma having uniform temperature, density, and composition in space and time. The energy deposited by α particles in the plasma is then obtained analytically when small angle scattering is the only mechanism for energy transfer. The results agree well with the earlier numerical results obtained by Cooper and Evans and Antal and Lee using numerical integration and the Sn method, respectively.",
"title": "Energy deposition of fast α particles in a fully ionized deuterium‐tritium plasma",
"URL": "https://aip.scitation.org/doi/abs/10.1063/1.863129",
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"Small-angle scattering",
"Physics",
"Convection–diffusion equation",
"Atomic physics",
"Ionization",
"Energy flux",
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"abstract": "The assessment of the Shutdown Dose Rate SDR due to neutron activation is a major safety issue for fusion devices and in the last decade several benchmark experiments have been conducted at JET ...",
"title": "The preparation of the Shutdown Dose Rate experiment for the next JET Deuterium-Tritium campaign",
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"abstract": "A solid deuteriumtritium fuel layer within a spherical inertial confinement fusion target will be driven uniform by βdecay energy if the target is held in an isothermal environment. The apparatus we constructed to verify this process provides an isothermal and radiationtight environment. Heat exchange between the target 20 K and the environment 4.2 K is regulated by controlling the helium exchange gas through a specially constructed manifold. A unique optical system maintained at low temperatures allows direct observation of the fuel layer uniformity. Tritium containment in the event of a target failure is assured by tungsteninert gas welding of the stainlesssteel structure. This system conveniently fits a standard vendor supplied 100l Dewar, and is designed to minimize boiloff and cooldown losses by means of an efficient helium vapor counterflow system. We have also incorporated a vibration isolation system to permit holographic interferometry imaging and evaluation of the fuel layers.",
"title": "Apparatus for verification of beta heating driven layer uniformity in solid deuterium–tritium",
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"abstract": "Steady-state thermal-hydraulic analyses were carried out for the DEMOSTARFIRE fusion reactor based on solid breeder blankets and pressurized water as the coolant. The results of the parametric studies show that a coolant in-tube design, .., coolant tubes embedded in solid breeder blanket, with a contact resistance between the coolant tube and the solid breeder tailored to maintain the operating temperature window .., the maximum and the minimum temperature imposed on the solid breeder is viable. However, design of such a solid breeder blanket will present serious challenges because of uncertainty in the thermophysical properties of breeder materials, the narrow operating temperature window, the close manufacturing tolerances necessary to control the gap conductance, the sensitivity of tritium inventory and tritium extraction to breeder temperature distribution, and the deleterious effect of neutron irradiation on breeder material properties. The study shows that even modest uncertainties in the thermal conductivity of solid breeders, interfacial gap conductances, and operating power levels can have significant impact on blanket design. Therefore, the designer should include the expected variations in these parameters. Experimental programs are needed to quantify the above factors and to develop methods .., insulated coatings for gap conductance control and in situ recovery of tritiummore via helium purge gas channels. less",
"title": "An Assessment Of Critical Thermal-Hydraulic Problems in A Deuterium-Tritium Solid Breeder Blanket",
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"abstract": "This paper uses neutron emission spectrometry NES, with the spectrometer TOFOR, to estimate the deuterium-tritium DT equivalent fusion yields of deuterium-only DD pulses at the tokamak JET. A...",
"title": "Component-wise deuterium-tritium fusion yield predictions with neutron emission spectrometry",
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"abstract": "A kind of fusion dianostics based on proton recoil method and magnetic analyzing technology is introduced. It can be used for the accurate diagnoses of plama tempreture, fuel density and neutron yield. A prototype is designed, using a high-powered Nd-Fe-B permanent dipole for magnetic analyzer, and proton position distribution in the focal plane is measured by CR-39 trajectory detector or PIN detector. The system is calibrated with a 239 Pu source, and a corresponding particle transport simulation program is worked out. The performance of the spectrometer is investigated with the Monte Carlo simulation, and neutron experiments are taken on the K-400 accelerator.",
"title": "Study of magnetic proton recoil technology for measurement of deuterium-tritium neutron spectrum",
"URL": "http://dx.doi.org/10.7498/aps.61.072902",
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"year_published": 2012,
"first_author": "Zhou Lin",
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"abstract": "The deuterium-tritium D-T ensuremath-to-neutron branching ratio was determined under inertial confinement fusion ICF conditions, where the center-of-mass energy of 14--24 keV is lower than that in previous accelerator-based experiments. A D-T branching ratio value of 4.2 ifmmodepmelsetextpmfi 2.0 ifmmodetimeselsetexttimesfi 10 was determined by averaging the results of two methods 1 a direct measurement of ICF D-T ensuremath-ray and neutron emissions using absolutely calibrated detectors, and 2 a separate cross-calibration against the D-He ensuremath-to-proton branching ratio. Neutron-induced backgrounds were significantly reduced as compared to traditional beam-target accelerator-based experiments due to the short pulse nature of ICF implosions and the use of gas Cherenkov ensuremath-ray detectors with fast temporal responses and inherent energy thresholds. These measurements of the D-T branching ratio in an ICF environment test several theoretical assumptions about the nature of 5 systems, including the dominance of the 32 resonance at low energies, the presence of the broad first excited state of He in the spectra, and the charge-symmetric nature of the capture processes in the mirror systems He and Li.",
"title": "Determination of the deuterium-tritium branching ratio based on inertial confinement fusion implosions",
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"year_published": 2012,
"first_author": "Yongho Kim",
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"abstract": "We investigate deuterium-tritium DT fusion cross sections in the presence of electromagnetic fields with high intensity and high frequency. With the help of the Kramers-Henneberger KH transformation, we show that the corresponding Coulomb barrier penetrability increases significantly due to the depression of the time-averaged potential barrier. As a result, we find that DT fusion cross sections can be enhanced depending effectively on a dimensionless quantity, which equals the ratio of the quiver oscillation amplitude to the geometrical touching radius of the deuterium and tritium nuclei. For, we predict that the fusion cross section is almost five times the value in the absence of electromagnetic fields, which implies that the famous Lawson criterion might be relaxed to some extent.",
"title": "Enhanced deuterium-tritium fusion cross sections in the presence of strong electromagnetic fields",
"URL": "https://journals.aps.org/prc/abstract/10.1103/PhysRevC.100.064610",
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"Electromagnetic field",
"Cross section (physics)",
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"year_published": 2019,
"first_author": "Wenjuan Lv",
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"entity": "tritium"
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"category": "Field Configuration",
"entity": "electromagnetic fields with high intensity and high frequency"
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"category": "Nuclear Fusion Technique",
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"sentence": "With the help of the Kramers-Henneberger KH transformation, we show that the corresponding Coulomb barrier penetrability increases significantly due to the depression of the time-averaged potential barrier.",
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"sentence": "As a result, we find that DT fusion cross sections can be enhanced depending effectively on a dimensionless quantity, which equals the ratio of the quiver oscillation amplitude to the geometrical touching radius of the deuterium and tritium nuclei.",
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"abstract": "We have calculated viscosity and mutual diffusion of deuterium-tritium DT in the warm, dense matter regime for densities from 5 to 20 gcm and temperatures from 2 to 10 eV, using both finite-temperature Kohn-Sham density-functional theory molecular dynamics QMD and orbital-free molecular dynamics OFMD. The OFMD simulations are in generally good agreement with the benchmark QMD results, and we conclude that the simpler OFMD method can be used with confidence in this regime. For low temperatures 3 eV and below, one-component plasma OCP model simulations for diffusion agree with the QMD and OFMD calculations, but deviate by 30 at 10 eV. In comparison with the QMD and OFMD results, the OCP viscosities are not as good as for diffusion, especially for 5 gcm where the temperature dependence is significantly different. The QMD and OFMD reduced diffusion and viscosity coefficients are found to depend largely, though not completely, only on the Coulomb coupling parameter, with a minimum in the reduced viscosity at 25, approximately the same position found in the OCP simulations. The QMD and OFMD equations of state pressure are also compared with the hydrogen two-component plasma model.",
"title": "Viscosity and mutual diffusion of deuterium-tritium mixtures in the warm-dense-matter regime",
"URL": "https://www.ncbi.nlm.nih.gov/pubmed/21230193",
"fields_of_study": [
"Physics",
"Viscosity",
"Reduced viscosity",
"Diffusion (business)",
"Atomic physics",
"Coupling (probability)",
"Warm dense matter",
"Hydrogen",
"Deuterium",
"Plasma",
"Thermodynamics"
],
"year_published": 2010,
"first_author": "Joel D. Kress",
"scholarly_citations_count": 56,
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"abstract": "Transmitted neutron spectra from slabs of beryllium, lead, stainless steel, ThOsub 2, Lisub 2COsub 3, and graphite, driven by a Haefely neutron generator operated at low intensity, were measured with a 2- 2-in. NE-213 detector at the LOTUS facility. These materials investigated under our fusion blanket neutronics program. In this paper, these experiments are analyzed with the two-dimensional code DOT3.5 and the three-dimensional code MCNP. The discrepancies on spectral integrals between 15 and 1 MeV are within 10 to 15 for empty cavity, 15-cm-thick lead, 18-cm beryllium, and 25-cm graphite slabs for both three-dimensional MCNP and two-dimensional DOT computations as compared to those obtained from the measured spectra much larger differences are found for 6.,2-cm-thick stainless steel, 15-cm Lisub 2COsub 3, and 27.7-cm ThOsub 2 slabs. Also, there is a considerable disagreement over pointwise spectra for a number of slabs.",
"title": "Transmitted Spectra of Single Slabs Driven by (Deuterium-Tritium) Neutrons at the Lotus Facility",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST89-A11963084",
"fields_of_study": [
"Neutron",
"Neutron generator",
"Atomic physics",
"Nuclear physics",
"Materials science",
"Blanket",
"Graphite",
"Spectral line",
"Beryllium",
"Deuterium",
"Neutron transport"
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"year_published": 1989,
"first_author": "Anil Kumar",
"scholarly_citations_count": 4,
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"abstract": "New experiments in a NIF-scale toroidal cylinder have resulted in true shadowgraphs of the DT ice surface. The spectral analysis of the images summed over -modes 2 through 256 reveal that the surface roughness reaches values just below 1.0 at temperatures of 19 K and above. Summing only modes 10, the partial surface roughness is below 0.7 at 19.5 K. These results indicate that native beta-layering will be sufficient to meet the NIF requirements for DT ice surface finish for both Be and CH ablating shells. The toroidal cylinder incorporates a linear heater along the cylindrical axis to test the concept of surface enhancement due to heat assisted beta-layering in DT. Additionally, with the use of this heater it is possible to symmetrize a pure D layer.",
"title": "Surface roughness measurements of beta-layered solid deuterium-tritium in toroidal geometries",
"URL": "https://core.ac.uk/display/71153641",
"fields_of_study": [
"Surface roughness",
"Toroid",
"Heat flux",
"Atomic physics",
"Materials science",
"Cylinder",
"Surface (mathematics)",
"Beta (plasma physics)",
"Deuterium",
"Surface finish"
],
"year_published": 1996,
"first_author": "James K. Hoffer",
"scholarly_citations_count": 20,
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"abstract": "The first experiments utilizing highpower radio waves in the ion cyclotron range of frequencies to heat deuteriumtritium DT plasmas have been completed on the Tokamak Fusion Test Reactor. Results from the initial series of experiments have demonstrated efficient core second harmonic tritium 2ΩT heating in parameter regimes approaching those anticipated for the International Thermonuclear Experimental Reactor. Observations are consistent with modeling predictions for these plasmas. Efficient electron heating via mode conversion of fast waves to ion Bernstein waves has been observed in DT, deuteriumdeuterium DD, and deuteriumhelium4 D4He plasmas with high concentrations of minority helium3 3He n3Hene10. Mode conversion current drive in DT plasmas...",
"title": "Ion cyclotron range of frequencies heating and current drive in deuterium–tritium plasmas",
"URL": "https://ui.adsabs.harvard.edu/abs/1995PhPl....2.2427P/abstract",
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"Ion",
"Atomic physics",
"Nuclear physics",
"Tokamak Fusion Test Reactor",
"Helium-3",
"Cyclotron",
"Nuclear fusion",
"Thermonuclear fusion",
"Plasma",
"Radio wave"
],
"year_published": 1995,
"first_author": "C. K. Phillips",
"scholarly_citations_count": 36,
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"abstract": "A next-generation neutron temporal diagnostic NTD capable of recording high-quality data for the highest anticipated yield cryogenic deuteriumtritium DT implosion experiments was recently installed at the Omega Laser Facility. A high-quality measurement of the neutron production width is required to determine the hot-spot pressure achieved in inertial confinement fusion experimentsa key metric in assessing the quality of these implosions. The design of this NTD is based on a fast-rise-time plastic scintillator, which converts the neutron kinetic energy to 350- to 450-nm-wavelength light. The light from the scintillator inside the nose-cone assembly is relayed 16 to a streak camera in a well-shielded location. An 200 reduction in neutron background was observed during the first high-yield DT cryogenic implosions compared to the current NTD installation on OMEGA. An impulse response of 40 10 ps was measured in a dedicated experiment using hard -rays from a planar target irradiated with a 10-ps short pulse from the OMEGA EP laser. The measured instrument response includes contributions from the scintillator rise time, optical relay, and streak camera.",
"title": "Neutron temporal diagnostic for high-yield deuterium–tritium cryogenic implosions on OMEGA",
"URL": "https://pubmed.ncbi.nlm.nih.gov/27250417/",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Streak camera",
"Neutron",
"Scintillator",
"Cryogenics",
"Nuclear physics",
"Implosion",
"Laser",
"Deuterium"
],
"year_published": 2016,
"first_author": "Christian Stoeckl",
"scholarly_citations_count": 33,
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{
"abstract": "Active interrogation using neutrons is an effective method for detecting shielded nuclear material. A lightweight, lunch-box-sized, battery-operated neutron source would enable new concepts of operation in the field. We have developed at-scale components for a highly portable, completely self-contained, pulsed Deuterium-Tritium DT neutron source producing 14 MeV neutrons with average yields of 107 ns. A gated, field ionization ion source using etched electrodes has been developed that produces pulsed ion currents up to 500 nA. A compact Cockcroft-Walton high voltage source is used to accelerate deuterons into a metal hydride target for neutron production. The results of full scale DT tests using the field ionization source are presented.",
"title": "Compact deuterium-tritium neutron generator using a novel field ionization source",
"URL": "http://www.osti.gov/scitech/biblio/22402648-compact-deuterium-tritium-neutron-generator-using-novel-field-ionization-source",
"fields_of_study": [
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"Neutron source",
"Neutron generator",
"Atomic physics",
"Nuclear physics",
"Chemistry",
"Ion source",
"Ionization",
"Field desorption",
"Deuterium",
"Neutron detection"
],
"year_published": 2014,
"first_author": "Jennifer Ellsworth",
"scholarly_citations_count": 4,
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},
{
"sentence": "A lightweight, lunch-box-sized, battery-operated neutron source would enable new concepts of operation in the field.",
"entities": [
{
"category": "Experimental Apparatus",
"entity": "neutron source"
},
{
"category": "Particle",
"entity": "neutron"
}
]
},
{
"sentence": "We have developed at-scale components for a highly portable, completely self-contained, pulsed Deuterium-Tritium DT neutron source producing 14 MeV neutrons with average yields of 107 ns.",
"entities": [
{
"category": "Particle",
"entity": "neutron"
},
{
"category": "Chemical Element or Compound",
"entity": "Deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "Tritium"
},
{
"category": "Chemical Element or Compound",
"entity": "Tritium"
},
{
"category": "Nuclear Fusion System Component",
"entity": "pulsed Deuterium-Tritium DT neutron source"
}
]
},
{
"sentence": "A gated, field ionization ion source using etched electrodes has been developed that produces pulsed ion currents up to 500 nA.",
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{
"category": "Experimental Apparatus",
"entity": "gated, field ionization ion source"
},
{
"category": "Nuclear Fusion System Component",
"entity": "etched electrodes"
}
]
},
{
"sentence": "A compact Cockcroft-Walton high voltage source is used to accelerate deuterons into a metal hydride target for neutron production.",
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{
"category": "Nuclear Fusion System Component",
"entity": "metal hydride target"
},
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{
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]
},
{
"sentence": "The results of full scale DT tests using the field ionization source are presented.",
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"category": "Experimental Apparatus",
"entity": "field ionization source"
},
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"category": "Nuclear Fusion Technique",
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]
}
]
},
{
"abstract": "In ITER and next step fusion reactors, the chosen materials for the first wall are Beryllium and Tungsten because of their good thermodynamic and mechanical properties, low level of erosion, neutron activation, and Tritium retention. However, radiation events due to the release of such high Z materials, can be responsible of plasma cooling, which can affect the ELM dynamics, trigger MHD instabilities, and inhibit the achievement of thermonuclear temperatures. For these reasons, over the years, methods to control the radiation level have been developed and integrated in the scenario design development. JET is the ideal testbed experiment to conduct radiation control studies being equipped with an ITER-like wall and able to operate with Tritium and Deuterium-Tritium fuel mixtures in plasmas with input power up to 33 MW. In this work, radiation control in JET ITER-like wall baseline plasmas during Tritium and Deuterium-Tritium baseline operations is reported, complimenting the work presented in. The behavior of radiation control methods has been investigated statistically. Such analysis suggests that, in Tritium hollow density profiles develop because of the high density level achieved at the plasma edge. This turns out to affect the ELM dynamics, exacerbating the radiation control. A possible solution to counter radiation build up is proposed and consists in exploiting the presence of error field correction coils to mitigate the ELM dynamics, and to induce density pump-out, thus affecting the density profile evolution.",
"title": "Radiation control in Tritium and Deuterium-Tritium JET baseline plasmas – part II",
"URL": "NaN",
"fields_of_study": [
"Tritium",
"Deuterium",
"Fusion power",
"Neutron generator",
"Nuclear physics",
"Nuclear engineering",
"Plasma",
"Materials science",
"Beryllium",
"Thermonuclear fusion",
"Physics",
"Neutron",
"Neutron source",
"Engineering"
],
"year_published": 2023,
"first_author": "L. Piron",
"scholarly_citations_count": 7,
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"entity": "thermonuclear temperatures"
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]
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"sentence": "For these reasons, over the years, methods to control the radiation level have been developed and integrated in the scenario design development.",
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"category": "Concept",
"entity": "radiation level"
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"entity": "methods to control the radiation level"
}
]
},
{
"sentence": "JET is the ideal testbed experiment to conduct radiation control studies being equipped with an ITER-like wall and able to operate with Tritium and Deuterium-Tritium fuel mixtures in plasmas with input power up to 33 MW.",
"entities": [
{
"category": "Nuclear Fusion Experimental Facility",
"entity": "JET"
},
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"category": "Nuclear Fusion System Component",
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"category": "Chemical Element or Compound",
"entity": "Tritium"
},
{
"category": "Chemical Element or Compound",
"entity": "Deuterium-Tritium"
},
{
"category": "Plasma property",
"entity": "plasmas with input power up to 33 MW"
}
]
},
{
"sentence": "In this work, radiation control in JET ITER-like wall baseline plasmas during Tritium and Deuterium-Tritium baseline operations is reported, complimenting the work presented in.",
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{
"category": "Nuclear Fusion Experimental Facility",
"entity": "JET"
},
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"entity": "Tritium"
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"entity": "Tritium"
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"entity": "Deuterium"
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]
},
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"sentence": "The behavior of radiation control methods has been investigated statistically.",
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}
]
},
{
"sentence": "Such analysis suggests that, in Tritium hollow density profiles develop because of the high density level achieved at the plasma edge.",
"entities": [
{
"category": "Chemical Element or Compound",
"entity": "Tritium"
},
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"category": "Plasma property",
"entity": "hollow density profiles"
},
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"entity": "plasma edge"
}
]
},
{
"sentence": "This turns out to affect the ELM dynamics, exacerbating the radiation control.",
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{
"category": "Plasma property",
"entity": "ELM dynamics"
},
{
"category": "Plasma event",
"entity": "ELMs"
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"entity": "radiation control"
}
]
},
{
"sentence": "A possible solution to counter radiation build up is proposed and consists in exploiting the presence of error field correction coils to mitigate the ELM dynamics, and to induce density pump-out, thus affecting the density profile evolution.",
"entities": [
{
"category": "Nuclear Fusion System Component",
"entity": "error field correction coils"
},
{
"category": "Plasma property",
"entity": "ELM dynamics"
},
{
"category": "Plasma property",
"entity": "density profile"
},
{
"category": "Plasma dynamic and behavior",
"entity": "density pump-out"
},
{
"category": "Plasma property",
"entity": "density profile evolution"
}
]
}
]
},
{
"abstract": "High rates for mesomolecular processes were found in a study of neutron spectra from muon-catalyzed fusion in low-density DT mixtures. An interpretation is given in terms of a reaction-kinetics model which includes hyperfine effects. The hyperfine components of the formation rates, first separated in this experiment, are large from 30 to 300 K. An unexpected temperature dependence for the transition rate between hyperfine states is found.",
"title": "Experimental Study of Muon-Catalyzed Fusion in Low-Density Deuterium-Tritium Gas",
"URL": "https://link.aps.org/doi/10.1103/PhysRevLett.53.1137",
"fields_of_study": [
"Physics",
"Hyperfine structure",
"Fusion",
"Atomic physics",
"Nuclear physics",
"Interpretation (model theory)",
"Low density",
"Muon-catalyzed fusion",
"Deuterium",
"Transition rate matrix",
"Tritium illumination"
],
"year_published": 1984,
"first_author": "W. H. Breunlich",
"scholarly_citations_count": 68,
"NER-RE": [
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},
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},
{
"abstract": "In this paper, neutron diagnostics is discussed as a supplier of alpha-particle information on the burning deuterium-tritium plasmas of next-step tokamaks such as the International Thermonuclear Experimental ReactorNext European Torus ITERNET, Ignitor, and the Burning Plasma Experiment BPX. Conceptual studies for such neutron measurements with neutron cameras and spectrometers are presented, and the potential information output is identified and assessed. Examples are given as to where direct alpha-particle information can be provided, and the relevance of neutron data as a source of indirect information is illustrated in view of the envisaged quality, scope, and availability of neutron measurements for various plasma conditions. Also discussed is how neutron diagnostics can serve as a plasma condition monitor for burn control purposes besides bringing experimental insight on the physics of fusion plasmas with a significant fast alpha-particle population.",
"title": "Alpha-particle information on burning deuterium-tritium plasmas from neutron measurements",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST92-A30079",
"fields_of_study": [
"Tokamak",
"Physics",
"Neutron",
"Neutron emission",
"Nuclear physics",
"IGNITOR",
"Population",
"Plasma diagnostics",
"Thermonuclear fusion",
"Neutron detection"
],
"year_published": 1992,
"first_author": "Jan Källne",
"scholarly_citations_count": 3,
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{
"sentence": "In this paper, neutron diagnostics is discussed as a supplier of alpha-particle information on the burning deuterium-tritium plasmas of next-step tokamaks such as the International Thermonuclear Experimental ReactorNext European Torus ITERNET, Ignitor, and the Burning Plasma Experiment BPX.",
"entities": [
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},
{
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{
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"entity": "Alpha-particle"
},
{
"category": "Chemical Element or Compound",
"entity": "Deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "Tritium"
},
{
"category": "Plasma property",
"entity": "Burning deuterium-tritium plasmas"
},
{
"category": "Detection and Monitoring Systems",
"entity": "Neutron diagnostics"
}
]
},
{
"sentence": "Conceptual studies for such neutron measurements with neutron cameras and spectrometers are presented, and the potential information output is identified and assessed.",
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"category": "Detection and Monitoring Systems",
"entity": "neutron cameras"
},
{
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}
]
},
{
"sentence": "Examples are given as to where direct alpha-particle information can be provided, and the relevance of neutron data as a source of indirect information is illustrated in view of the envisaged quality, scope, and availability of neutron measurements for various plasma conditions.",
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"category": "Particle",
"entity": "alpha-particle"
},
{
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},
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},
{
"category": "Detection and Monitoring Systems",
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}
]
},
{
"sentence": "Also discussed is how neutron diagnostics can serve as a plasma condition monitor for burn control purposes besides bringing experimental insight on the physics of fusion plasmas with a significant fast alpha-particle population.",
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{
"category": "Particle",
"entity": "neutron"
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"entity": "plasma condition"
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"entity": "fusion plasmas"
},
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"category": "Physical Process",
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}
]
}
]
},
{
"abstract": "How the plasma stability index beta and the fusion power density influence three performance parameters of fusion reactors burning deuterium-tritium and four advanced fusion fuel cycles was determined. The performance parameters include the total power produced per unit length of the reactor, the mass per unit length, and the specific mass in kilograms per kilowatt. The scaling of these parameters with beta and fusion power density was examined for a common set of conservative engineering assumptions on the allowable wall loading limits, the maximum magnetic field existing in the plasma, the average blanket mass density, etc. It was found that one should employ an entirely different strategy for the design of an engineering test reactor, designed to test components under high wall loadings and neutron fluences, than one would employ in designing a power plant reactor intended to produce the cheapest possible thermal power. An ETR should not be merely a scaled-down power plant reactor, but should operate at substantially different values of beta and plasma power density, and in some circumstances even use a different confinement concept and fusion fuel cycle.",
"title": "Performance scaling of fusion reactors using the deuterium-tritium and advanced fuel cycles",
"URL": "http://www.osti.gov/scitech/biblio/5705201-performance-scaling-fusion-reactors-using-deuterium-tritium-advanced-fuel-cycles",
"fields_of_study": [
"Nuclear engineering",
"Neutron",
"Nuclear physics",
"Materials science",
"Thermal power station",
"Power density",
"Fusion power",
"Beta (plasma physics)",
"Plasma stability",
"Power station",
"Neutron flux"
],
"year_published": 1985,
"first_author": "J. Reece Roth",
"scholarly_citations_count": 2,
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"entity": "plasma stability index beta"
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},
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]
}
]
},
{
"abstract": "New experiments in a NIF-scale toroidal cylinder have resulted in true shadowgraphs of the DT ice surface. The spectral analysis of the images summed over ℓ-modes 2 through 256 reveal that the surface roughness reaches values just below 1.0 μm at temperatures of 19 K and above. Summing only modes ℓ 10, the partial surface roughness is below 0.7 μm at 19.5 K. These results indicate that native beta-layering will be sufficient to meet the NIF requirements for DT ice surface finish for both Be and CH ablating shells.The toroidal cylinder incorporates a linear heater along the cylindrical axis to test the concept of surface enhancement due to heat assisted beta-layering in DT. Additionally, with the use of this heater it is possible to symmetrize a pure D2 layer.",
"title": "Surface Roughness Measurements of Beta-Layered Solid Deuterium-Tritium in Toroidal Geometries",
"URL": "https://digital.library.unt.edu/ark:/67531/metadc669084/m2/1/high_res_d/257456.pdf",
"fields_of_study": [
"Toroid",
"Materials science",
"BETA (programming language)",
"Cylinder",
"Surface roughness",
"Surface finish",
"Deuterium",
"Layering",
"Surface (topology)",
"Mechanics",
"Plasma",
"Nuclear physics",
"Physics",
"Composite material",
"Geometry",
"Mathematics",
"Botany",
"Computer science",
"Biology",
"Programming language"
],
"year_published": 1996,
"first_author": "James K. Hoffer",
"scholarly_citations_count": 20,
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"entity": "CH"
},
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},
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"entity": "toroidal cylinder"
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"entity": "D2"
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}
]
},
{
"abstract": "A DT neutron yield diagnostic based on the reactions, 63Cun,2n62Cuβ and 65Cun,2n 64 Cuβ, has been fielded at the National Ignition Facility NIF. The induced copper activity is measured using a NaI γ-γ coincidence system. Uncertainties in the 14-MeV DT yield measurements are on the order of 7 to 8. In addition to measuring yield, the ratio of activities induced in two, well-separated copper samples are used to measure the relative anisotropy of the fuel ρR to uncertainties as low as 5.",
"title": "Copper activation deuterium-tritium neutron yield measurements at the National Ignition Facility",
"URL": "https://pubmed.ncbi.nlm.nih.gov/23126920/",
"fields_of_study": [
"Analytical chemistry",
"Physics",
"Neutron emission",
"Isotopes of copper",
"Nuclear physics",
"National Ignition Facility",
"Neutron activation analysis",
"Yield (chemistry)",
"Copper",
"Deuterium",
"Tritium"
],
"year_published": 2012,
"first_author": "Gary Wayne Cooper",
"scholarly_citations_count": 15,
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{
"abstract": "Alpha heating experiments in the Tokamak Fusion Test Reactor TFTR and in the Joint European Torus JET 1997 DTE1 campaign arc reexamined. In TFTR supershots central electron heating of both deut...",
"title": "Alpha heating, isotopic mass, and fast ion effects in deuterium–tritium experiments",
"URL": "http://www.diva-portal.org/smash/record.jsf?pid=diva2:1375688",
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"Jet (fluid)",
"Ion",
"Nuclear physics",
"Materials science",
"Joint European Torus",
"Tokamak Fusion Test Reactor",
"Electron heating",
"Deuterium",
"Tritium"
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"year_published": 2018,
"first_author": "Robert Budny",
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"abstract": "Maximizing the neutron yield to obtain energy gain is the ultimate goal for inertial confinement fusion. Nonuniformities seeded by target and laser perturbations can disrupt neutron production via the RayleighTaylor instability growth. To understand the effects of perturbations on the neutron yield of cryogenic DT implosions on the Omega Laser Facility, two-dimensional DRACO simulations have been performed to systematically investigate each perturbation source and their combined effects on the neutron-yield performance. Two sources of nonuniformity accounted for the neutron-yield reduction in DRACO simulations target offset from the target chamber center and laser imprinting. The integrated simulations for individual shots reproduce the experimental yield-over-clean YOC ratio within a factor of 2 or better. The simulated neutron-averaged ion temperatures Ti is only about 1015 higher than meas...",
"title": "Two-dimensional simulations of the neutron yield in cryogenic deuterium-tritium implosions on OMEGA",
"URL": "https://scitation.aip.org/content/aip/journal/pop/17/10/10.1063/1.3491467",
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"Physics",
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"Neutron",
"Atomic physics",
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"Omega",
"Rayleigh–Taylor instability",
"Laser",
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"year_published": 2010,
"first_author": "Suxing Hu",
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"abstract": "The University of Illinois hydrodynamic burn code, AFBURN, has been used to model the performance of homogeneous D-T, D2, and catalyzed deuterium ICF targets. Yields and gains are compared for power-producing targets. AFBURN is a one-dimensional, two-temperature, single-fluid hydrodynamic code with non-local fusion product energy deposition. The initial conditions for AFBURN are uniformly compressed targets with central hot spots. AFBURN predicts that maximum D2 target gains are obtained for target ρR and spark ρR about seven times larger than the target and spark ρR for maximum D-T target gains, that the maximum D2 target gain is approximately one third of the maximum D-T target gain, and that the corresponding yields are approximately equal. By recycling tritium and 3 He from previous targets, D2 target performance can be improved by about 10.",
"title": "Burn performance of deuterium-tritium, deuterium-deuterium, and catalyzed deuterium ICF targets",
"URL": "http://iopscience.iop.org/0029-5515/23/8/008/pdf/0029-5515_23_8_008.pdf",
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"Deposition (phase transition)",
"Catalysis",
"Atomic physics",
"Materials science",
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"Homogeneous"
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"abstract": "AbstractThe AYMAN research project has been initiated to formulate the main structure of a prototypical experimental fusion and fusion-fission hybrid reactor blanket in cylindrical geometry. This geometry is consistent with most of the current fusion and hybrid reactor design concepts in respect to neutronic considerations.In this project, the fusion chamber is simulated by a cavity with a diameter of 1.6 inside a cylindrical blanket. Fusion neutrons of 14 MeV are produced by a movable target along the axis of the cylinder. The movable neutron source allows simulation of a line source for integral experiments, which is a result of the linear nature of the Boltzmann transport equation.The calculations have shown that a blanket with a 13-cm-thick natural UO2 fuel zone and a 17-cm-thick Li2O zone has a self-sustaining tritium breeding for the fusion driver. By an appropriate dispersion of the Li2O zone inside the graphite reflector, it became possible to decrease the neutron leakage out of the reflector...",
"title": "Preliminary Design Studies of a Cylindrical Experimental Hybrid Blanket with Deuterium-Tritium Driver",
"URL": "http://www.osti.gov/scitech/biblio/5450453-preliminary-design-studies-cylindrical-experimental-hybrid-blanket-deuterium-tritium-driver",
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"Neutron",
"Fusion",
"Neutron source",
"Nuclear physics",
"Materials science",
"Cylinder",
"Hybrid reactor",
"Blanket",
"Line source",
"Deuterium"
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"year_published": 1986,
"first_author": "Sümer Şahin",
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"abstract": "The effect of reducing the aspect ratio on the confinement of deuterium-tritium fusion products, .., alpha particles, in tokamaks is discussed. It is shown that for low-aspect-ratio tokamak reactors, the alpha-particle heating efficiency can be similar to conventional tokamaks at the same time, the alpha-particle confinement time can be much shorter than that of conventional tokamaks. Thus, one can facilitate alpha-particle ash removal while maintaining high alpha-particle heating efficiency by reducing the aspect ratio.",
"title": "Confinement of alpha particles in low-aspect-ratio deuterium-tritium ignited Tokamaks",
"URL": "http://cat.inist.fr/?aModele=afficheN&cpsidt=2332981",
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"Fusion",
"Ignition system",
"Aspect ratio",
"Nuclear physics",
"Distribution function",
"Materials science",
"Deuterium",
"Tritium",
"Alpha particle"
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"year_published": 1998,
"first_author": "Lijian Qiu",
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"abstract": "Results of discrete ordinates radiation transport calculations are presented for the proposed tokamak ignition and burn control experiment ZEPHYR. As a first step, baryte concrete with 0.15 wt Bsub 4C was identified as an optimum concrete for the shielding fitting tightly around the torus and some attached devices. This shielding material with a maximum thickness of 70 cm allows personnel to enter the experiment hall just a few hours after termination of a worst-case burn discharge sequence. Inside the vacuum vessel, delayed dose rates amount to several tens of remh after only 50 of plasma burn for waiting times that are typical for maintenance and repair, thus, remote handling equipment is required. Bootstrapped radiation transport calculations for neutral beam injectors show them to be strongly activated after the worst-case discharge sequence with typical dose rates of some remh. Thus shielding is required around the injector boxes and most repair tasks have to be performed remotely. Delayed dose rates outside the torus shielding in front of typical straight diagnostic ducts with diameters of 15 to 25 cm are shown to be significant but hands-on maintenance of the diagnostic equipment will be possible with some restrictions on working time.",
"title": "Prompt and Delayed Radiation Shielding Calculations for the ZEPHYR Deuterium-Tritium Ignition Experiment",
"URL": "https://ans.org/pubs/journals/fst/a_20762",
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"Injector",
"Ignition system",
"Beam (structure)",
"Nuclear physics",
"Materials science",
"Electromagnetic shielding",
"Deuterium",
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"year_published": 1982,
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"abstract": "Solid deuterium-tritium D-T fuel layers for inertial confinement fusion experiments were formed inside of a 2 mm diameter beryllium shell and were characterized using phase-contrast enhanced -ray imaging. The solid D-T surface roughness is found to be 0.4 for modes 7-128 at 1.5 K below the melting temperature. The layer roughness is found to increase with decreasing temperature, in agreement with previous visible light characterization studies. However, phase-contrast enhanced -ray imaging provides a more robust surface roughness measurement than visible light methods. The new -ray imaging results demonstrate clearly that the surface roughness decreases with time for solid D-T layers held at 1.5 K below the melting temperature.",
"title": "Solid Deuterium-Tritium Surface Roughness In A Beryllium Inertial Confinement Fusion Shell",
"URL": "https://core.ac.uk/display/71317152",
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"Composite material",
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"Shell (structure)",
"Beryllium",
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"abstract": "Recent radio-frequency heating experiments on the Tokamak Fusion Test Reactor TFTR have focused on developing tools for both pressure and current profile control in deuteriumtritium DT plasmas. A new antenna was added to investigate pressure profile control utilizing direct ion Bernstein wave IBW heating. This was the first time direct IBW heating was explored on TFTR. Plasma heating and driven poloidal flows are observed. Previously heating and current drive via mode-converted IBW waves had been demonstrated in non-DT plasmas but efforts in DT plasmas had been unsuccessful. This lack of success had been ascribed to the presence of a small 7Li minority ion population. In the most recent experiments 6Li was used exclusively for machine conditioning and mode-conversion heating consistent with theory is now observed in DT plasmas.",
"title": "Ion cyclotron range of frequencies heating and flow generation in deuterium–tritium plasmas",
"URL": "http://scitation.aip.org/content/aip/journal/pop/5/5/10.1063/1.872840",
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"Physics",
"Ion",
"Atomic physics",
"Ion cyclotron resonance",
"Tokamak Fusion Test Reactor",
"Range (particle radiation)",
"Population",
"Cyclotron",
"Deuterium",
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"year_published": 1998,
"first_author": "James R. Wilson",
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"abstract": "The alpha α-particle and neutron emission spectra in a deuterium-tritium plasma accompanied with neutral-beam-injection NBI heating are evaluated in a consistent way by solving the BoltzmannFokkerPlanck equations for deuteron, triton, and α-particle simultaneously. It is shown that owing to the existence of non-Maxwellian tail component in fuel-ion distribution function due to NBI andor nuclear elastic scattering, the generation rate of the energetic 4 MeV α-particle increases significantly. When 20 MW intense deuterium beam with 1 MeV beam-injection energy is injected into an 800 m3 plasma Te10 keV, ne6.21019 m3, the enhancement of the fraction of the power carried by α-particles with energy above 4 3.9 MeV to total α-particle power is almost twice 1.5 times as much from the value for Gaussian distribution. A verification scenario for the modification of the emission spectrum by using the gamma γ-ray-generating B9eα,nγC12 reaction is also presented.",
"title": "Modification of alpha-particle emission spectrum in beam-injected deuterium-tritium plasmas",
"URL": "http://ui.adsabs.harvard.edu/abs/2009PhPl...16d2507M/abstract",
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"Neutron emission",
"Atomic physics",
"Elastic scattering",
"Fusion power",
"Spectral line",
"Deuterium",
"Alpha particle",
"Plasma",
"Emission spectrum"
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"year_published": 2009,
"first_author": "Hideaki Matsuura",
"scholarly_citations_count": 16,
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"abstract": "A new compact magnetic proton recoil MPR neutron spectrometer has been designed for precise measurement of deuterium-tritium DT neutrons. This design is presented emphasizing the magnetic analyzing system, which is based on a compact quadrupole-dipole QD electromagnet. The focal plane detector FPD is also discussed with respect to application for the next step. The characteristics of the MPR spectrometer were calculated by using Monte Carlo simulation. A preliminary experiment was performed to test the magnetic analyzing system and the proton images of the FPD. Since the QD electromagnet design allows for a larger foil thickness and solid angle to be utilized, the MPR spectrometer defined in this paper can achieve neutron detection efficiency more than 5 107 at an energy resolution of 1.5 for measuring DT neutrons.",
"title": "Development of a compact magnetic proton recoil spectrometer for measurement of deuterium-tritium neutrons",
"URL": "https://aip.scitation.org/doi/full/10.1063/1.4939010",
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"Physics",
"Neutron",
"Nuclear physics",
"Monte Carlo method",
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"Plasma diagnostics",
"Proton",
"Deuterium",
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"first_author": "Jianfu Zhang",
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"abstract": "Because alpha particle losses can have a significant influence on tokamak reactor viability, the loss of deuteriumtritium alpha particles from the Tokamak Fusion Test Reactor TFTR has been measured under a wide range of conditions. In TFTR, first orbit loss and stochastic toroidal field ripple diffusion are always present. Other losses can arise due to magnetohydrodynamic instabilities or due to waves in the ion cyclotron range of frequencies. No alpha particle losses have yet been seen due to collective instabilities driven by alphas. Ion Bernstein waves can drive large losses of fast ions from TFTR, and details of those losses support one element of the alpha energy channeling scenario.",
"title": "Alpha particle losses from Tokamak Fusion Test Reactor deuterium-tritium plasmas",
"URL": "https://aip.scitation.org/doi/10.1063/1.871983",
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"Tokamak",
"Physics",
"Ion",
"Nuclear physics",
"Tokamak Fusion Test Reactor",
"Range (particle radiation)",
"Cyclotron",
"Magnetohydrodynamic drive",
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"Plasma"
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"year_published": 1996,
"first_author": "D. S. Darrow",
"scholarly_citations_count": 26,
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"abstract": "Abstract In this work, the anomalous transport driven by the ion temperature gradient instability is investigated in an anisotropic deuterium-tritium D-T plasma. The anisotropic factor α, defined as the ratio of perpendicular temperature to parallel temperature, is introduced to describe the temperature anisotropy in the equilibrium distribution function. The linear dispersion relation in local kinetic limit is derived, and then numerically evaluated to study the dependence of mode frequency on the anisotropic factor α of D and the fraction of T particle ε T by choosing three sets of typical parameters, denoted as the cyclone base case, ITER and CFETR cases. Based on the linear results, the mixing length model approximation is adopted to analyze the quasi-linear particle and energy fluxes for D and T. It is found that choosing small α and large ε T is beneficial for the confinement of particle and energy for D and T. This work may be helpful for the estimation of turbulent transport level in the ITER and CFETR devices.",
"title": "Anomalous transport driven by ion temperature gradient instability in an anisotropic deuterium-tritium plasma",
"URL": "NaN",
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"Instability",
"Deuterium",
"Work (physics)",
"Plasma",
"Ion",
"Tokamak",
"Kinetic energy",
"Electron temperature",
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"Atomic physics",
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"Nuclear physics",
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"Condensed matter physics",
"Mechanics",
"Classical mechanics",
"Optics",
"Meteorology",
"Quantum mechanics"
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"year_published": 2022,
"first_author": "Debing ZHANG",
"scholarly_citations_count": 2,
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"abstract": "In this work, we studied the stopping power of deuterium-tritium DT plasmas mixed with impurities to the injected charged particles. Based on the Brown-Preston-Singleton model, the analytical expression for the change ratio of stopping power denoted by η induced by impurities in DT plasmas is developed, in which both classical short-distance collision part and quantum correction contribution are purely linear response to the impurity concentration ξ_, while the classical long-range collision brings about higher-order nonlinear response to ξ_. Furthermore, the expression for change ratio of deposition depth denoted by χ of charged particles induced by impurities in DT plasmas is also derived. As applications, we systemically investigated the energy loss of α particles deposited into a hot dense DT plasma mixed with impurity XXC, Si, Ge, where the temperature and density of DT are smaller than 10 keV and 500 gcm and the concentration of Xξ_ is less than 5. The numerical results suggest that for the case of C mixed into DT, both change ratios of stopping power and deposition depth of α particles .., η and χ are linear response to the concentration of C ξ_ ii for the case of Si mixed into DT, the second-order nonlinear response of η and χ to ξ_ cannot be ignored when the densities of DT are larger than 200 gcm and iii for the case of Ge mixed into DT, the second- and third-order nonlinear response of η and χ to ξ_ are very remarkable because of the higher ionization degree and heavier atomic mass of Ge. The formulas and findings in this work may be helpful to the research of internal confinement fusion ICF related implosion physics and may provide useful theoretical guidance and data for the design of ICF target.",
"title": "Stopping power of hot dense deuterium-tritium plasmas mixed with impurities to charged particles.",
"URL": "https://ui.adsabs.harvard.edu/abs/2020PhRvE.101e3209F/abstract",
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"Atomic mass",
"Atomic physics",
"Materials science",
"Implosion",
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"Deuterium",
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"year_published": 2020,
"first_author": "Zhen-Guo Fu",
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"abstract": "Abstract The effects of fusion-born alpha α particles on zonal flow ZF driven by collisionless trapped electron mode CTEM turbulence are analytically investigated, using gyrokinetic and bounce kinetic theories in the deuteriumtritium DT tokamak plasmas. It is found that ZF growth rate is increased by α particles because of the reduction of polarization shielding as well as enhancement of CTEM instability. The results of this paper are qualitatively consistent with the enhancement of the level of residual ZF by α particles in Cho and Hahm 2019 Nucl. Fusion 59 066026. The parametric dependence of ZF growth rate is also analyzed. The increment of ZF growth rate is further enhanced by α particles with higher fraction and steeper density profile. Besides, the dependence of ZF growth rate on electron temperature T could be changed qualitatively by the presence of α particles when T T . Moreover, the difference of ZF growth rates in the presence of α particles with slowing down and equivalent Maxwellian distribution functions is very weak. These results could be very important for accurate prediction of the confinement in the future burning plasmas such as International Thermonuclear Experimental Reactor and China Fusion Engineering Test Reactor.",
"title": "Effects of alpha particles on the CTEM driven zonal flow in deuterium–tritium tokamak plasmas",
"URL": "NaN",
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"abstract": "Our work is in the context of the French laser megajoule project, about fusion by inertial confinement. The project leads to the problem of characterizing the inner surface, of the approximately spherical target, by optical shadowgraphy techniques. Our work is entirely based on the basic idea that optical shadowgraphy produces caustics of systems of optical rays, which contain a great deal of 3D information about the surface to be characterized. We develop a method of 3D reconstruction based upon this idea plus a small perturbations technique. Although computations are made in the special spherical case, the method is in fact general and may be extended to several other situations.",
"title": "Observer for a thick layer of solid deuterium-tritium using backlit optical shadowgraphy and interferometry",
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"Laser Mégajoule",
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"abstract": "Alpha particle confinement is essential to achieving ignition in deuteriumtritium plasmas, and measuring the energy and spatial distributions of fusion alphas is one of the most challenging tasks in plasma diagnostics research. Confined trapped-alpha energy spectra and radial density profiles in the Tokamak Fusion Test Reactor TFTR have been obtained using the pellet charge exchange PCX diagnostic, which measures high energy Eα0.53.5 MeV, trapped alphas vv0.048 at a single time slice Δt1 ms with a spatial resolution of Δr5 cm. PCX measures the energy spectrum of energetic helium neutrals resulting from charge exchange interactions of alphas incident on the ablation cloud surrounding small boron and lithium pellets injected radially into TFTR. The success of PCX has led to a number of important results on the behavior of alphas in TFTR. The measured alpha energy spectrum in the plasma core of sawtooth-free discharges is consistent with the alphas being well confined and slowing down cla...",
"title": "Pellet charge exchange measurements of confined alphas in deuterium–tritium plasmas (invited) (abstract)",
"URL": "https://aip.scitation.org/doi/abs/10.1063/1.1149453",
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"Nuclear physics",
"Materials science",
"Tokamak Fusion Test Reactor",
"Plasma diagnostics",
"Spectral line",
"Lithium",
"Helium",
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"abstract": "A comprehensive knowledge of the properties of high-energy-density plasmas is crucial to understanding and designing low-adiabat, inertial confinement fusion ICF implosions through hydrodynamic simulations. Warm-dense-matter WDM conditions are routinely accessed by low-adiabat ICF implosions, in which strong coupling and electron degeneracy often play an important role in determining the properties of warm dense plasmas. The WDM properties of deuteriumtritium DT mixtures and ablator materials, such as the equation of state, thermal conductivity, opacity, and stopping power, were usually estimated by models in hydro-codes used for ICF simulations. In these models, many-body and quantum effects were only approximately taken into account in the WMD regime. Moreover, the self-consistency among these models was often missing. To examine the accuracy of these models, we have systematically calculated the static, transport, and optical properties of warm dense DT plasmas, using first-principles FP metho...",
"title": "Impact of first-principles properties of deuterium–tritium on inertial confinement fusion target designsa)",
"URL": "http://ui.adsabs.harvard.edu/abs/2015PhPl...22e6304H/abstract",
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"Monte Carlo method",
"Many-body problem",
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"year_published": 2015,
"first_author": "Suxing Hu",
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"abstract": "We report on numerical studies of real viscous effects on the implosion characteristics of imploded DT micro-targets. We use the implicit ePLAS code to perform 2D simulations of spherical and slightly ellipsoidal DT shells on DT gas filled 40 μm diameter voids. Before their final implosions the shells have been nearly adiabatically compressed up to 102 or 103 gcm3 densities. While the use of conventional artificial viscosity can lead to high central densities for initially spherical shells, we find that a real physical viscosity from ion-ion collisions can give a high 20 keV central temperature but severely reduced central density 200 gcm3, while the elliptical shells evidence 2 distortion of the heated central fuel region. These results suggest that the general use of artificial viscosities in Inertial Confinement Fusion ICF modeling may have lead to overly optimistic yields for current NIF targets and that polar direct drive with more energy for the imploding capsule may be needed for ultimate ICF success.",
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"abstract": "We determine the dependence of key Inertial Confinement Fusion ICF hot spot simulation properties on the deuterium-tritium fuel adiabat, here modified by addition of energy to the cold shell. Variation of this parameter reduces the simulation to experiment discrepancy in some, but not all, experimentally inferred quantities. Using simulations with radiation drives tuned to match experimental shots N120321 and N120405 from the National Ignition Campaign NIC, we carry out sets of simulations with varying amounts of added entropy and examine the sensitivities of important experimental quantities. Neutron yields, burn widths, hot spot densities, and pressures follow a trend approaching their experimentally inferred quantities. Ion temperatures and areal densities are sensitive to the adiabat changes, but do not necessarily converge to their experimental quantities with the added entropy. This suggests that a modification to the simulation adiabat is one of, but not the only explanation of the observed simulation to experiment discrepancies. In addition, we use a theoretical model to predict 3D mix and observe a slight trend toward less mixing as the entropy is enhanced. Instantaneous quantities are assessed at the time of maximum neutron production, determined dynamically within each simulation. These trends contribute to ICF science, as an effort to understand the NIC simulation to experiment discrepancy, and in their relation to the high foot experiments, which features a higher adiabat in the experimental design and an improved neutron yield in the experimental results.",
"title": "Sensitivity of inertial confinement fusion hot spot properties to the deuterium-tritium fuel adiabat",
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"Nucleon",
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"year_published": 2015,
"first_author": "Jeremy Melvin",
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{
"abstract": "Abstract The safeguard aspects of Cm-244- a nuclear waste product in LWRs in a cylindrical hybrid blanket driven by a D,T fusion neutron source have been analyzed. Cm-244 has been investigated for two different applications 1. As a neutron multiplier between the first wall and the fuel zone in a blanket with ThO2. 2. As a component of the mixed fuel, ThO2-Cm244O2, used for power flattening in a hybrid blanket. The calculations have shown that a relatively small reactor driven with 100 MWth fusion power could product about 5 kgyear Cm-245, enough to provide nuclear fuel for up to 50 explosives. The study suggests an extension of the safeguarding regulations prior to the commercial introduction of fusion reactors in the energy market.",
"title": "Cm-244 as Multiplier and Breeder in a ThO2 Hybrid Blankets of Deuterium-Tritium Driven Source",
"URL": "https://www.sciencedirect.com/science/article/pii/S1018363918308754",
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"Neutron",
"Materials science",
"Fusion power",
"Blanket",
"Nuclear fuel",
"Safeguard",
"Deuterium",
"Tritium",
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"year_published": 1990,
"first_author": "Tawfik A. Al-Kusayer",
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"abstract": "One of the main concerns about the ignition and burn of deuterium-tritium DT plasma is the negative effect of impurities that can get into the thermonuclear fuel during target compression on the ignition of an inertial confinement fusion ICF target. So, the ignition condition of the spherical DT plasma of the ICF target in the presence of high-density carbon impurities at an arbitrary concentration is found. The ignition criterion of nuclear fusion plasmas is investigated using a two-temperature model derived from a common model. The ignition criterion is described by a surface in the three-dimensional space. This surface is defined by the electron and ion temperatures, Te and Ti, and the plasma density times the hot spot dimension, ρR, for different concentrations of impurities. In this paper, a two-temperature laser induced shock wave is used. We found that one needs a laser intensity of 7.5 1021 Wcm2, a pulse duration of 1ps, and an energy of 0.44 kJ that induces a compression of κ 4 to ignite a pure DT pre-compressed target at about 500 gcm3. Given the constant intensity of the laser, the increase in the carbon impurity concentration increases the alpha energy deposition in the igniter zone on the other hand, the temperature of the igniter zone decreases as a result of high losses of power densities, so that for impurity values of more than 20, practically no hot spots are formed.One of the main concerns about the ignition and burn of deuterium-tritium DT plasma is the negative effect of impurities that can get into the thermonuclear fuel during target compression on the ignition of an inertial confinement fusion ICF target. So, the ignition condition of the spherical DT plasma of the ICF target in the presence of high-density carbon impurities at an arbitrary concentration is found. The ignition criterion of nuclear fusion plasmas is investigated using a two-temperature model derived from a common model. The ignition criterion is described by a surface in the three-dimensional space. This surface is defined by the electron and ion temperatures, Te and Ti, and the plasma density times the hot spot dimension, ρR, for different concentrations of impurities. In this paper, a two-temperature laser induced shock wave is used. We found that one needs a laser intensity of 7.5 1021 Wcm2, a pulse duration of 1ps, and an energy of 0.44 kJ that induces a compression of κ 4 to ignit...",
"title": "Effects of carbon impurity on the ignition of deuterium-tritium targets under the relativistic shock waves",
"URL": "https://aip.scitation.org/doi/10.1063/1.5087298",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Ion",
"Ignition system",
"Atomic physics",
"Nuclear fusion",
"Shock wave",
"Impurity",
"Thermonuclear fusion",
"Plasma"
],
"year_published": 2019,
"first_author": "M. Najjar",
"scholarly_citations_count": 2,
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{
"abstract": "The Joint European Torus JET is the only tokamak in the world able to operate in Deuterium-Tritium DT plasmas. A successful DT experimental campaign, the DTE2, has recently been carried out, providing unique opportunities for studying both physics and technological aspects. In particular, it allowed us to investigate and benchmark the solutions adopted to attenuate the significant 14 MeV neutron flux, needed to enable high-resolution gamma-ray spectroscopy measurements on a tokamak. While in inertial confinement experiments, gamma-rays and neutrons are discriminated through time-of-flight techniques in magnetic confinement experiments, the neutron attenuators are a key element to allow gamma-ray measurements in order to reestablish the 1 105 to 1 background to signal ratio. In this paper, the role of the reference neutron attenuators at JET, based on LiH, has been analyzed and described.",
"title": "Role of neutron attenuators for gamma-ray measurements in deuterium-tritium magnetic confinement plasmas.",
"URL": "NaN",
"fields_of_study": [
"Deuterium",
"Nuclear physics",
"Tritium",
"Neutron",
"Plasma",
"Materials science",
"Plasma diagnostics",
"Gamma ray",
"Atomic physics",
"Physics"
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"year_published": 2022,
"first_author": "D Rigamonti",
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{
"abstract": "The radioactivity, biological hazard potential, and afterheat levels in the deuterium-deuterium D-D fuel cycle fusion reactor, SATYR, have been evaluated for two types of structural materials ferritic steel HT-9 and sintered aluminum product. Results are compared to the corresponding levels in the deuterium-tritium D-T fuel cycle systems, STARFIRE and WITAMIR-I, both during operation and after plant decomissioning. The influence of blanket replacements on the radioactivity levels has been considered in the comparative analysis. It has been found that the long-term radioactivity level 100 to 1000 yr after plant shutdown in the ferritic steel blanket of the SATYR design is somewhat higher, by a factor of 2 to 6, than that found for a D-T reactor system employing the same structural alloy. The high levels are attributed to the softer spectrum and the larger structure volume fraction encountered in the D-D machines. However, the levels during plant operation about30 yr are comparable. Isotopic tailoring and elemental substitution in alloys to reduce the long-term radioactivity levels in the SATYR design are discussed. It is found that three orders of magnitude reduction in radioactivity levels can be achieved by isotopically tailoring the molybdenum in the ferritic steel to 100 sup 97Mo. The more elemental substitution of vanadium for nickel and molybdenum in ferritic steels is shown to reduce long-term radioactivity levels by four orders of magnitude. These low levels at long times after shutdown are below those found for blankets using aluminum alloy structure. The results make clear that elemental composition should be a primary consideration in alloy formulation if the goal of a low radioactivity level in fusion reactor radwaste is to be achieved. less",
"title": "Induced radioactivity and influence of materials selection in deuterium-deuterium and deuterium-tritium fusion reactors",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST83-A20861",
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"Radiochemistry",
"Materials science",
"Induced radioactivity",
"Fusion power",
"Blanket",
"Alloy",
"Vanadium",
"Molybdenum",
"Deuterium",
"Tritium"
],
"year_published": 1983,
"first_author": "Mahmoud Z. Youssef",
"scholarly_citations_count": 7,
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"sentence": "Results are compared to the corresponding levels in the deuterium-tritium D-T fuel cycle systems, STARFIRE and WITAMIR-I, both during operation and after plant decomissioning.",
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"sentence": "The influence of blanket replacements on the radioactivity levels has been considered in the comparative analysis.",
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"category": "Nuclear Fusion System Component",
"entity": "blanket"
}
]
},
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"sentence": "It has been found that the long-term radioactivity level 100 to 1000 yr after plant shutdown in the ferritic steel blanket of the SATYR design is somewhat higher, by a factor of 2 to 6, than that found for a D-T reactor system employing the same structural alloy.",
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"sentence": "Isotopic tailoring and elemental substitution in alloys to reduce the long-term radioactivity levels in the SATYR design are discussed.",
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"abstract": "The use of strong magnetic fields to augment the output energy of inertial confinement fusion experiments at the National Ignition Facility is of high interest. It offers the potential of reducing electron thermal conduction and increasing hot-spot alpha heating with little to no change in hohlraum behavior. In these magnetically assisted ignition experiments, the ultimate goal is to add a B-field in the form of a pulse ranging from 25 to 60 T to a high-performing hohlraum implosion several microseconds before impingement of the laser beams. This requires eliminating metallic components in the target and replacing them with electrically nonconducting materials. However, the strong eddy currents generated by the rapidly increasing high B-field, which were calculated to be as high as 2000 K, can heat the hohlraum. In this paper, we examine the transient effects of this rapid temperature change on the behavior of the target as well as the fuel layer composed typically of deuterium and tritium. Using simulations and calculations for limiting case scenarios, we find that the effect of the heating is not restrictive toward the performance of the target or the quality of the deuterium-tritium ice.",
"title": "Analysis of Dynamic Behavior of the Target and the Deuterium-Tritium Ice in Magnetic-Field Assisted Implosions",
"URL": "NaN",
"fields_of_study": [
"Hohlraum",
"National Ignition Facility",
"Implosion",
"Inertial confinement fusion",
"Deuterium",
"Ignition system",
"Materials science",
"Plasma",
"Fusion power",
"Magnetic field",
"Thermal conduction",
"Atomic physics",
"Nuclear physics",
"Nuclear engineering",
"Physics",
"Thermodynamics",
"Quantum mechanics",
"Engineering",
"Composite material"
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"year_published": 2023,
"first_author": "S. Bhandarkar",
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{
"abstract": "Glass capsules were imploded in direct drive on the OMEGA laser to look for anomalous degradation in deuteriumtritium DT yield and changes in reaction history with H3e addition. Such anomalies have previously been reported for DH3e plasmas but had not yet been investigated for DTH3e. Anomalies such as these provide fertile ground for furthering our physics understanding of inertial confinement fusion implosions and capsule performance. Anomalous degradation in the compression component of yield was observed, consistent with the factor of 2 degradation previously reported by Massachusetts Institute of Technology MIT at a 50 H3e atom fraction in D2 using plastic capsules. However, clean calculations .., no fuel-shell mixing predict the shock component of yield quite well, contrary to the result reported by MIT but consistent with Los Alamos National Laboratory results in D2H3e Wilson et al., J. Phys. Conf....",
"title": "Anomalous yield reduction in direct-drive deuterium/tritium implosions due to H3e additiona)",
"URL": "http://ui.adsabs.harvard.edu/abs/2009PhPl...16e6312H/abstract",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Yield (engineering)",
"Atomic physics",
"Nuclear physics",
"Isotopes of helium",
"Helium-3",
"Helium",
"Deuterium",
"Tritium",
"Plasma"
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"year_published": 2009,
"first_author": "Hans W. Herrmann",
"scholarly_citations_count": 46,
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"abstract": "The timing of alpha losses, with respect to the various phases of a disruption, and the impact location of the losses are characterized during high fusion power operation of TFTR with deuterium and tritium fuels. Characterization of alpha losses is important for the design of future fusion devices such as ITER. In addition, characterization of the alpha losses with respect to the disruption evolution helps in the understanding of the dynamics of the disruption process and related MHD events such as sawtooth crashes. Disruptions are characterized as having several standard phases, applicable to most disruptions in all tokamaks precursor, thermal quenches and current quench. Most of the losses are observed to occur during the thermal quench phases. In high beta disruptions, alpha losses start abruptly during the growth of MHD precursors, just before the onset of the thermal quench. The initial burst of losses, lasting as little as 100 mu , can release a significant fraction one third of the total disruption induced losses during the thermal quench. An inventory of alpha particles suggests that the alpha loss distribution during disruptions might be quite different from that expected during non-disruptive discharges. There are no obvious differences between fast fusion product losses during deuterium-deuterium DD and deuterium-tritium DT disruptions, aside from the large alpha loss component in DT discharges",
"title": "Characterization of alpha particle loss during disruptions in TFTR during deuterium-tritium operation",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/36/4/I07/meta",
"fields_of_study": [
"Tokamak",
"Nuclear engineering",
"Fusion",
"Nuclear physics",
"Materials science",
"Fusion power",
"Beta (plasma physics)",
"Magnetohydrodynamics",
"Deuterium",
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"Alpha particle"
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"year_published": 1996,
"first_author": "A.C. Janos",
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"abstract": "High or enhanced confinement Hmode plasmas have been obtained for the first time with nearly equal concentrations of deuterium and tritium in hightemperature, high poloidal beta plasmas in the Tokamak Fusion Test Reactor TFTR. Tritium fueling was provided mainly through highpower neutral beam injection NBI with powers up to 31 MW and beam energies of 90110 keV. A transition to a circular limiter Hmode configuration has been obtained, following a programmed rapid decrease of the plasma current. Isotope effects, due to the presence of tritium, led to different behavior for deuteriumdeuterium DD and deuteriumtritium DT Hmodes relative to confinement, edge localized magnetohydrodynamic modes ELMs, and ELM effects on fusion products. However, the threshold power for the Hmode transition was the same in DD and DT. Some of the highest values of the global energy confinement time, τE, have been achieved on TFTR during the ELMfree phase of DT Hmode plasmas. Enhancements of τE greater than four times the Lmode have been attained.",
"title": "Deuterium–tritium high confinement (H‐mode) studies in the Tokamak Fusion Test Reactor",
"URL": "https://scitation.aip.org/content/aip/journal/pop/2/6/10.1063/1.871490",
"fields_of_study": [
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"Beam (structure)",
"Atomic physics",
"Nuclear physics",
"Neutral beam injection",
"Tokamak Fusion Test Reactor",
"Beta (plasma physics)",
"Limiter",
"Deuterium",
"Tritium",
"Plasma"
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"year_published": 1995,
"first_author": "C.E. Bush",
"scholarly_citations_count": 26,
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{
"abstract": "Angular neutron fluxes leaking from the surface of beryllium slab assemblies have been measured with irradiation of deuterium-tritium neutrons. The experiment was performed using the time-of-flight technique with an NE-213 scintillation detector. The measured neutron energy range was from 50 keV to 15 MeV. The thicknesses of the slabs were 50.8 and 152.4 mm, and the measured angles of the angular fluxes were 0.0, 12.2, 24.9, 41.8, and 66.8 deg. The experimental results have been compared with the results calculated by the Monte Carlo codes, MORSE-DD and MCNP, using the data of beryllium in the JENDL-3PRI, ENDFB-IV, and Los Alamos National Laboratory nuclear data files. The results calculated with these files showed discrepancies of 20 to 30 from the experimental results. It was pointed out that the angular distributions of an elastic cross section and the total cross section of an inelastic reaction for 14.8-MeV neutrons in the files were insufficient to reproduce the measured spectra.",
"title": "Measurement and analysis of an angular neutron flux on a beryllium slab irradiated with deuterium-tritium neutrons",
"URL": "https://www.ans.org/pubs/journals/nse/a_23504",
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"Neutron",
"Scintillator",
"Nuclear physics",
"Neutron temperature",
"Nuclear data",
"Beryllium",
"Neutron cross section",
"Deuterium",
"Neutron flux"
],
"year_published": 1987,
"first_author": "Yukio Oyama",
"scholarly_citations_count": 29,
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"sentence": "The measured neutron energy range was from 50 keV to 15 MeV.",
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"abstract": "A parametric study of the burn performance measured by the fuel energy gain of compressed deuterium-tritium fuel microspheres, with parameters of interest to inertial confinement fusion, has been performed by 1-D numerical radiation-hydrodynamics simulations. Both volume-ignited and centrally ignited either initially isobaric or isochoric configurations are considered. An overview is given of the relevant ignition conditions. For the first time a scaling law is presented for the limiting gain of volume-ignited fuels. Scaling laws are also given for the limiting gain of centrally ignited assemblies, which have the same functional dependences as predicted by previous analytical models, but different numerical coefficients. The advantage of isochoric assemblies over isobaric ones is confirmed, but found to be smaller than previously reported. The potentials of volume-ignited and of centrally ignited, isobaric assemblies as functions of the energy, density and pressure are also critically compared.",
"title": "Thermonuclear Burn Performance of Volume-Ignited and Centrally Ignited Bare Deuterium-Tritium Microspheres",
"URL": "http://ui.adsabs.harvard.edu/abs/1995JaJAP..34.1980./abstract",
"fields_of_study": [
"Inertial confinement fusion",
"Fusion ignition",
"Isobaric process",
"Ignition system",
"Nuclear physics",
"Chemistry",
"Volume (thermodynamics)",
"Mechanics",
"Nuclear fusion",
"Thermonuclear fusion",
"Isochoric process"
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"year_published": 1995,
"first_author": "Stefano Atzeni",
"scholarly_citations_count": 70,
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"abstract": "Nuclear heat deposition rates in the structural components of a fusion reactor have been measured directly with a microcalorimeter incorporated with an intense deuterium-tritium D- T neutron source, the Fusion Neutronics Source FNS at the Japan Atomic Energy Research Institute JAERI, under the framework of the JAERIU.S. Department of Energy U.S. DOE collaborative program on fusion neutronics. Heat deposition rates at positions up to 200 mm of depth in a Type 304 stainless steel assembly bombarded with D-T neutrons were measured along with single probe experiments. The measured heating rates were compared with comprehensive calculations in order to verify the adequacy of the currently available database relevant to the nuclear heating. In general, calculations with data of JENDL-3 and ENDL-85 libraries gave good agreement with experiments for all single probe materials, whereas RMCCS, based on ENDFB-V, suffered from unreasonable overestimation in the heating number. It was demonstrated that the nuclearthermal coupled calculation is a powerful tool to analyze the time-dependent temperature change due to the heat transfer in the probe materials. The analysis for the Type 304 stainless steel assembly, based on JENDL-3, demonstrated that the calculation, in general, was in good agreement with the measurement up to 200 mmmore of depth along the central axis of the assembly. 31 refs., 16 figs., 4 tabs. less",
"title": "Direct nuclear heating measurements and analyses for structural materials induced by deuterium-tritium neutrons",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST95-A30404",
"fields_of_study": [
"Neutron",
"Neutron source",
"Nuclear physics",
"Thermal",
"Fusion power",
"Heat transfer",
"Deuterium",
"Tritium",
"Neutron transport"
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"year_published": 1995,
"first_author": "Y. Ikeda",
"scholarly_citations_count": 4,
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"abstract": "The-matrix analysis of nuclear systems has been partially validated by applying the technique to the system and comparing the predicted-ray spectrum with historical data.-matrix analysis of the similar system was then used to predict the-ray spectral shape for the deuterium-tritium DT reaction. The resulting spectra have been used in the analysis of DT implosions on the Omega laser where the-ray interaction rate was measured by a gas Cherenkov detector. Comparison of predictions to experiment confirmed the presence of both 16.75 and MeV-ray contributions analysis, using-matrix spectra, yielded a ratio of-ray emission from a transition to the intermediate excited state to that from a transition to the ground state of, substantiating the first spectral measurement of the DT fusion ray in an inertial fusion environment.",
"title": "First spectral measurement of deuterium-tritium fusion γ rays in inertial fusion experiments",
"URL": "https://link.aps.org/doi/10.1103/PhysRevC.104.024610",
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"Cherenkov detector",
"Spectral shape analysis",
"Excited state",
"Atomic physics",
"Omega",
"Spectral line",
"Deuterium",
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"year_published": 2021,
"first_author": "Colin Horsfield",
"scholarly_citations_count": 8,
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"abstract": "AbstractThe SORGENTINA-RF project aims to develop a 14 MeV fusion neutron source to produce medical radioisotopes with special focus on 99 Mo. The facility is based on a positive ion source with an acceleration stage to produce a deuterium D and tritium T ion beam that, impacting on a titanium-coated rotating target, allows fusion reactions to take place. Maximizing the neutron production rate is one of the main issues to be addressed in the project and the optimization of some key parameters of the ion beam is of paramount importance in this regard. In this study, a methodology is discussed to reach a definition of the beam characteristics for an effective and sustainable operation of the plant. The most convenient layout that has been found out is based on a single ion source fed by a deuterium and tritium gas mixture. Eventually, a series of considerations about the operation of the ion source and fuel cycle have been drawn.",
"title": "On the definition of the deuterium-tritium ion beam parameters for the SORGENTINA-RF fusion neutron source",
"URL": "https://link.springer.com/content/pdf/10.1140/epjp/s13360-022-03060-4.pdf",
"fields_of_study": [
"Deuterium",
"Algorithm",
"Materials science",
"Analytical Chemistry (journal)",
"Chemistry",
"Computer science",
"Physics",
"Nuclear physics",
"Chromatography"
],
"year_published": 2022,
"first_author": "Nicola Fonnesu",
"scholarly_citations_count": 3,
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"abstract": "A waste management concept that employs irradiation of fission products in fusion reactor blankets is evaluated. The purpose of the irradiation is to reduce the toxicity of the material to be commi...",
"title": "Reduction in the toxicity of fission product wastes through transmutation with deuterium-tritium fusion neutrons",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/NT80-A32436",
"fields_of_study": [
"Fission products",
"Nuclear fission product",
"Nuclear transmutation",
"Radiochemistry",
"Chemistry",
"Fusion power",
"Technetium-99",
"Waste disposal",
"Tritium",
"Radioactive waste"
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"year_published": 1980,
"first_author": "Theodore A. Parish",
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"abstract": "The potential performance, in deuterium-tritium plasmas, of a new enhanced confinement regime with reversed magnetic shear is assessed. The equilibrium conditions for an ERS mode plasma are estimated by solving the plasma transport equations using the thermal and particle diffusivities measured in a short duration ERS mode discharge in the Tokamak Fusion Test Reactor. The plasma performance depends strongly on Zeff and neutral beam penetration to the core. The steady-state projections typically have a central electron density of 2.51020 m3 and nearly equal central electron and ion temperatures of 10 keV. In time-dependent simulations the peak fusion power, 25 MW, is twice the steady-state level. Peak performance occurs during the density rise when the central ion temperature is close to the optimal value of 15 keV. The simulated pressure profiles can be stable to ideal magnetohydrodynamic instabilities wi...",
"title": "Deuterium-tritium simulations of the enhanced reversed shear mode in the Tokamak Fusion Test Reactor",
"URL": "https://www.osti.gov/servlets/purl/293438",
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"Physics",
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"Ion",
"Magnetic confinement fusion",
"Atomic physics",
"Electron temperature",
"Fusion power",
"Tokamak Fusion Test Reactor",
"Plasma",
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"year_published": 1997,
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"abstract": "The transport equation of Antal and Lee has been solved analytically to obtain the energy flux of..cap alpha.. particles in a fully ionized deuterium-tritium plasma having uniform temperature, density, and composition in space and time. The energy deposited by..cap alpha.. particles in the plasma is then obtained analytically when small angle scattering is the only mechanism for energy transfer. The results agree well with the earlier numerical results obtained by Cooper and Evans and Antal and Lee using numerical integration and the Ssub method, respectively.",
"title": "Energy deposition of fast. cap alpha. particles in a fully ionized deuterium-tritium plasma",
"URL": "http://www.osti.gov/scitech/biblio/5233618-energy-deposition-fast-cap-alpha-particles-fully-ionized-deuterium-tritium-plasma",
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"abstract": "We derive a dispersion relation for the damping of acoustic waves in equi-molar deuteriumtritium DT gas due to radiation coupling and electron thermal conduction and discuss its significance for inertial confinement fusion ICF targets with high-Z shells surrounding a central DT fuel region. As the shell implodes around DT fuel in such a target, shocks and waves are transmitted through the DT gas. If the shell is perturbed due to drive non-uniformity or manufacturing imperfection, these shocks and waves may be perturbed as well, and can potentially re-perturb the shell. This can complicate calculation of shell stability and implosion asymmetry and in general make the target less robust against implosion non-uniformity. Damping of perturbations in DT gas can alleviate these complications. Also, damping of low-order modes, which is primarily due to radiation coupling, can drive the DT gas to an isobaric and isothermal equilibrium configuration during ignition. We find that for the range of common ignition temperatures in targets with high-Z shells, keV, damping of low-order modes is significant for areal densities in the broad range of. This suggests it is advantageous to design these targets to achieve areal densities at ignition within this range. Furthermore, we derive a simple constraint between areal density and temperature, where is in keV, such that DT gas undergoing equilibrium ignition is optimally robust against non-uniformity.",
"title": "Radiation and electron thermal conduction damping of acoustic perturbations in igniting deuterium-tritium gas",
"URL": "http://ui.adsabs.harvard.edu/abs/2019JPlPh..85f9006G/abstract",
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"abstract": "Fusion reactor is considered as one of the solutions for the sustaining development of nuclear energy. International Thermonuclear Experimental Reactor ITER is the biggest fusion reactor research plan in the world. High-intensity D-T fusion neutron generator can generate 14 MeV neutrons, and it matches the neutrons generated in ITER and be competently used for imitating the neutron environment in nuclear fusion reactor, which is important for the relevant experimental researches of blanket materials of fusion reactors. It can also be used for validating the correctness and reliability of the simulations and analyses in fusion basic studies, and can guide the subsequent material improvement and innovation of calculation methodology. A rotating tritium target system for D-T fusion neutron generator with a neutron yield of 1012 -1, .., a high intensity D-T fusion neutron generator, is proposed in this paper and the design, main parameters, technical difficulties and heat transfer enhancement method are introduced. The key and innovative technology of this rotating target system is the integration of the sprayed water cooling, mechanical seal and magnetic fluid seal technologies, which focuses on the heat transfer of the high heat power density in the target system. The most important technical index is that the maximum temperature on the target should not be above 200 as the tritium ions run away heavily from the tritium target when the target temperature is bigger than 200. To investigate the heat transfer characteristics of this rotating target system, the effects of water layer thickness, water flow rate and rotating speed on the heat transfer of this rotating target system are analyzed by computational fluid dynamics method. And the heat transfer processes of the target system under different heat power densities are also simulated and studied. The analysis results show that big water layer thickness, big water flow rate and high rotating speed are good for the heat transfer enhancement of the rotating target system, but the effects of the changes of the water layer thickness and water flow rate on the heat transfer process are both very small. Due to the design index, the heat power density on the target should be under a limit value, which is about 12 kWcm-2 in the calculation results of this paper.",
"title": "Heat transfer analysis of rotating tritium target of deuterium-tritium fusion neutron generator",
"URL": "http://dx.doi.org/10.7498/aps.64.102901",
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"abstract": "An effect of nuclear elastic scattering NES on the energy transfer to plasma ions and electrons during a neutral beam injection NBI and α-particle heating operations is examined on the basis of the Boltzmann-Fokker-Planck BFP equation for a beam ion and an α-particle in deuterium-tritium thermonuclear plasmas. The BFP calculations show that the enhancement in the fraction of the NBI heating power deposited to ions due to NES becomes appreciable when the beam energy is larger than 1MeV. How the NES effect is influenced by the plasma condition is discussed.",
"title": "Effect of nuclear elastic scattering on ion heating characteristics in deuterium-tritium thermonuclear plasmas",
"URL": "https://ui.adsabs.harvard.edu/abs/2006PhPl...13f2507M/abstract",
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"Ion",
"Atomic physics",
"Elastic scattering",
"Fusion power",
"Neutral beam injection",
"Deuterium",
"Nuclear fusion",
"Thermonuclear fusion",
"Plasma"
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"year_published": 2006,
"first_author": "Hideaki Matsuura",
"scholarly_citations_count": 37,
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"abstract": "Abstract The performance of fusion devices relies strongly on the good confinement of energetic particles EPs. Therefore, the investigation of EP transport by magnetohydrodynamic instabilities is one of the key aspects in the development of plasma scenarios. Alfvénic instabilities in particular can lead to significant losses of alpha particles that are essential for plasma self-heating. A so-called afterglow scheme has been developed to study the destabilization of Alfvén eigenmodes AEs by alpha particles and associated EP transport in the JET tokamak. In this work, the linear stability of AEs is discussed for the partial afterglow phase in a JET deuterium plasma discharge and for the full afterglow phase in a projected deuteriumtritium DT plasma. Thanks to recent upgrades in the tokamak transport code TRANSP, one can account for the contributions of different EP species to mode stability. Analysis of deuterium plasmas shows that AE growth rates are extremely sensitive to the energy and distribution of fast ions. An increase in fast ion energy can lead to more unstable AEs. In the afterglow phase of projected DT plasmas, it is EPs that mostly drive the AEs. However, the drive by alpha particles is comparable to that by beam ions and their contribution to the net growth rate might be hard to separate. According to the discussed projections, the destabilization of AEs might be ineffective because the background plasma damping significantly exceeds the EP drive. In this case, the development of an alternative plasma scenario that allows us to overcome such damping would be required in future experiments.",
"title": "Alfvén eigenmode stability in a JET afterglow deuterium plasma and projections to deuterium–tritium plasmas",
"URL": "https://iopscience.iop.org/article/10.1088/1361-6587/acb844/pdf",
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"entity": "full afterglow phase"
}
]
},
{
"sentence": "Thanks to recent upgrades in the tokamak transport code TRANSP, one can account for the contributions of different EP species to mode stability.",
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"category": "Nuclear Fusion Device Type",
"entity": "tokamak"
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"entity": "mode stability"
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"category": "Particle",
"entity": "EP species"
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},
{
"sentence": "Analysis of deuterium plasmas shows that AE growth rates are extremely sensitive to the energy and distribution of fast ions.",
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"category": "Particle",
"entity": "deuterium"
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"category": "Particle",
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"category": "Physics Entity",
"entity": "energy"
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"entity": "energy"
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"category": "Plasma property",
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]
},
{
"sentence": "An increase in fast ion energy can lead to more unstable AEs.",
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"category": "Physics Entity",
"entity": "fast ion energy"
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]
},
{
"sentence": "In the afterglow phase of projected DT plasmas, it is EPs that mostly drive the AEs.",
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"category": "Particle",
"entity": "EPs"
},
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"category": "Plasma dynamic and behavior",
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"category": "Chemical Element or Compound",
"entity": "DT"
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},
{
"sentence": "However, the drive by alpha particles is comparable to that by beam ions and their contribution to the net growth rate might be hard to separate.",
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"category": "Particle",
"entity": "alpha particles"
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},
{
"sentence": "According to the discussed projections, the destabilization of AEs might be ineffective because the background plasma damping significantly exceeds the EP drive.",
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"category": "Plasma property",
"entity": "background plasma damping"
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{
"sentence": "In this case, the development of an alternative plasma scenario that allows us to overcome such damping would be required in future experiments.",
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"category": "Plasma property",
"entity": "damping"
},
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"category": "Concept",
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}
]
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]
},
{
"abstract": "AbstractAn alternative mixed beam neutral beam injector MNBI for fusion reactors is proposed that eliminates the conventional isotope separation system ISS in the fuel cycle. The principal advantage of the alternative system is a capital and operating cost savings in the fuel cycle, as the ISS employs cryogenic distillation at liquid-hydrogen temperatures to effect a separation of hydrogen isotopes and to eliminate a buildup of normal hydrogen in the recycled fuel. Possible additional advantages of the alternative method involve an improvement in overall safety and a reduction of the amount of tritium in the fuel cycle. The alternative heating system uses an electromagnetic separation in the MNBI to limit the buildup of normal hydrogen. Calculations indicate that an MNBI can be reasonably optimized in the case of an upgraded injection system for the Tokamak Fusion Test Reactor.",
"title": "Mixed Deuterium-Tritium Neutral Beam Injection: An Alternative Heating Method for Fusion Reactors",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST89-A29111",
"fields_of_study": [
"Nuclear engineering",
"Air separation",
"Nuclear physics",
"Materials science",
"Isotope separation",
"Fusion power",
"Neutral beam injection",
"Heating system",
"Tokamak Fusion Test Reactor",
"Hydrogen",
"Deuterium"
],
"year_published": 1989,
"first_author": "Lawrence Ruby",
"scholarly_citations_count": "NaN",
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"sentence": "The alternative heating system uses an electromagnetic separation in the MNBI to limit the buildup of normal hydrogen.",
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"sentence": "Calculations indicate that an MNBI can be reasonably optimized in the case of an upgraded injection system for the Tokamak Fusion Test Reactor.",
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"category": "Nuclear Fusion Device Type",
"entity": "Tokamak"
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"category": "Nuclear Fusion System Component",
"entity": "injection system"
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"category": "Theory and Calculation",
"entity": "Calculations"
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"category": "Nuclear Fusion Experimental Facility",
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{
"abstract": "Conceptual design of an electrochemically induced deuterium-tritium fusion power reactor has been carried out. A double-tube-type fuel cell is proposed for efficient electrolysis and to provide a large cathode area. The fuel cell tubes are assembled like a pressurized water reactor PWR control rod cluster. The tritium fuel is continuously fed through the cluster rod to the cell. The voltage for the electrolysis is supplied through the rod. The tritium breeding Lisub 2O is contained in a hexagonal blanket through which coolant tubes penetrate. The fuel cell tube is inserted in the coolant tube and the water coolant flows through the annuli.",
"title": "Electrochemically Induced Deuterium-Tritium Fusion Power Reactor — Preliminary Design of a Reactor System",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST89-A29159",
"fields_of_study": [
"Control rod",
"Nuclear engineering",
"Electrolytic cell",
"Electrolysis",
"Nuclear physics",
"Materials science",
"Fusion power",
"Blanket",
"Pressurized water reactor",
"Cathode",
"Coolant"
],
"year_published": 1989,
"first_author": "Y. Oka",
"scholarly_citations_count": "NaN",
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"sentence": "Conceptual design of an electrochemically induced deuterium-tritium fusion power reactor has been carried out.",
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"sentence": "A double-tube-type fuel cell is proposed for efficient electrolysis and to provide a large cathode area.",
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"sentence": "The fuel cell tubes are assembled like a pressurized water reactor PWR control rod cluster.",
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]
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"sentence": "The voltage for the electrolysis is supplied through the rod.",
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"sentence": "The tritium breeding Lisub 2O is contained in a hexagonal blanket through which coolant tubes penetrate.",
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"sentence": "The fuel cell tube is inserted in the coolant tube and the water coolant flows through the annuli.",
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"entity": "annuli"
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"category": "Chemical Element or Compound",
"entity": "water"
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{
"abstract": "The stopping power of a compressed and highly ionized deuterium-tritium DT and uranium U plasma for α particles at very high temperatures T 5 keV is examined theoretically with the dimensional continuation method. We show that with increasing density of U, both the magnitude and width of the resonance peak in the stopping power as a function of the α particle energy, increases because of the ions, while the penetration distance of the α particles decreases. A simple relation of decreasing penetration distance as a function of plasma density is observed, which may be useful for inertial confinement fusion experiments. Moreover, by comparing the results with the case of a DT plasma mixed with beryllium, we find that the effect of a higher Z plasma is stronger, with regard to energy loss as well as the penetration distance of α particles, than that of a lower Z plasma.",
"title": "Theoretical studies on the stopping power of deuterium-tritium mixed with uranium plasmas for α particles",
"URL": "http://www.osti.gov/scitech/biblio/22299666-theoretical-studies-stopping-power-deuterium-tritium-mixed-uranium-plasmas-particles",
"fields_of_study": [
"Penetration (firestop)",
"Inertial confinement fusion",
"Physics",
"Ion",
"Atomic physics",
"Ionization",
"Beryllium",
"Deuterium",
"Alpha particle",
"Plasma"
],
"year_published": 2014,
"first_author": "Zhigang Wang",
"scholarly_citations_count": 8,
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{
"abstract": "The purpose of the experiments described in this paper was to expose samples of polymeric materials to a mixture of deuterium-tritium DT gas at elevated temperature and pressure to investigate the effects .. damage on the materials. The materials and exposure parameters were chosen with to be relevant to proposed uses of similar materials in inertial fusion ignition experiments at the National Ignition Facility. Two types of samples were exposed and tested. The first type consisted of 10 4-lead ribbon cables of fine manganin wire insulated with polyimide. Wires of this type are proposed for use in thermal shimming of hohlraums and the goal of this experiment was to measure the change in electrical resistance of the insulation due to tritium exposure. The second type of sample consisted of 20 planar polymer samples that may be used as ignition capsule materials. The exposure was at 34.5 GPa 5010 psia and 70 C for 48 hours. The change in electrical resistance of the wire insulation will be presented. The results for capsule materials will be presented in a separate paper in this issue.",
"title": "Exposure of NIF relevant polymeric samples to deuterium-tritium gas at elevated temperature and pressure",
"URL": "https://digital.library.unt.edu/ark:/67531/metadc874490/",
"fields_of_study": [
"Inertial confinement fusion",
"Fusion ignition",
"Ignition system",
"Composite material",
"Materials science",
"National Ignition Facility",
"Manganin",
"Polyimide",
"Electrical resistance and conductance",
"Tritium illumination"
],
"year_published": 2006,
"first_author": "Peter S. Ebey",
"scholarly_citations_count": 3,
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"abstract": "Recent advances in shock timing experiments and analysis techniques now enable shock measurements to be performed in cryogenic deuterium-tritium DT ice layered capsule implosions on the National Ignition Facility NIF. Previous measurements of shock timing in inertial confinement fusion implosions were performed in surrogate targets, where the solid DT ice shell and central DT gas were replaced with a continuous liquid deuterium D2 fill. These previous experiments pose two surrogacy issues a material surrogacy due to the difference of species D2 vs. DT and densities of the materials used and a geometric surrogacy due to presence of an additional interface icegas previously absent in the liquid-filled targets. This report presents experimental data and a new analysis method for validating the assumptions underlying this surrogate technique. Comparison of the data with simulation shows good agreement for the timing of the first three shocks, but reveals a considerable discrepancy in the timing of the 4th shock in DT ice layered implosions. Electron preheat is examined as a potential cause of the observed discrepancy in the 4th shock timing.",
"title": "Shock timing measurements and analysis in deuterium-tritium-ice layered capsule implosions on NIF",
"URL": "http://www.osti.gov/scitech/biblio/22252076-shock-timing-measurements-analysis-deuterium-tritium-ice-layered-capsule-implosions-nif",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Electron",
"Cryogenics",
"Atomic physics",
"National Ignition Facility",
"Computational physics",
"Plasma diagnostics",
"Deuterium",
"Tritium",
"Shock (mechanics)"
],
"year_published": 2014,
"first_author": "Harry Robey",
"scholarly_citations_count": 28,
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"entity": "interface"
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"entity": "ice"
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"entity": "shocks"
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{
"abstract": "Recently, it has been demonstrated that radioactive selfheating in a solid can induce preferential sublimation from thicker, warmer layers to thinner, cooler ones, thus tending to make the layers become uniform in thickness. Following experiments in pure T2, we have investigated solid deuteriumtritium DT in optical cells with isothermal boundaries. Backlighting permits direct observations with a telescope and a video camera. As the temperature is lowered, we follow the stages of condensation, freezing, and subsequent layer equilibration or isotropization. Measured rate constants for freshly prepared DT samples agree well with the theoretically determined value of 26.6 min. Due to the impedance presented by 3 He in the vapor space, the rate constants for solid layers made from aged DT increase by nearly 12 minday. Equilibrated shells of solid DT exhibit slow optical degradation, presumably due to 3He accumulation at grain boundaries. The optical effects can be reduced by annealing near the triple point.",
"title": "Uniform solid deuterium–tritium fuel layers resulting from radioactively induced sublimation",
"URL": "https://ui.adsabs.harvard.edu/abs/1989JVSTA...7.1161H/abstract",
"fields_of_study": [
"Analytical chemistry",
"Isothermal process",
"Atomic physics",
"Chemistry",
"Sublimation (phase transition)",
"Grain boundary",
"Hydrogen",
"Triple point",
"Deuterium",
"Annealing (metallurgy)",
"Reaction rate constant"
],
"year_published": 1989,
"first_author": "J. K. Hoffer",
"scholarly_citations_count": 22,
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"sentence": "Following experiments in pure T2, we have investigated solid deuteriumtritium DT in optical cells with isothermal boundaries.",
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"entity": "deuterium-tritium (DT)"
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"sentence": "Backlighting permits direct observations with a telescope and a video camera.",
"entities": []
},
{
"sentence": "As the temperature is lowered, we follow the stages of condensation, freezing, and subsequent layer equilibration or isotropization.",
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{
"sentence": "Measured rate constants for freshly prepared DT samples agree well with the theoretically determined value of 26.6 min.",
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"sentence": "Due to the impedance presented by 3 He in the vapor space, the rate constants for solid layers made from aged DT increase by nearly 12 minday.",
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"abstract": "The first several campaigns of laser fusion experiments at the National Ignition Facility NIF included a family of high-sensitivity scintillatorphotodetector neutron-time-of-flight nTOF detectors for measuring deuteriumdeuterium DD and DT neutron yields. The detectors provided consistent neutron yield Yn measurements from below 109 DD to nearly 1015 DT. The detectors initially demonstrated detector-to-detector Yn precisions better than 5, but lacked in situ absolute calibrations. Recent experiments at NIF now have provided in situ DT yield calibration data that establish the absolute sensitivity of the 4.5 differential tissue harmonic imaging DTHI detector with an accuracy of 10 and precision of 1. The 4.5 nTOF calibration measurements also have helped to establish improved detector impulse response functions and data analysis methods, which have contributed to improving the accuracy of the Yn measurements. These advances have also helped to extend the usefulness of nTOF measurements of ion temperature and downscattered neutron ratio neutron yield 1012 MeV divided by yield 1315 MeV with other nTOF detectors.",
"title": "Deuterium-tritium neutron yield measurements with the 4.5 m neutron-time-of-flight detectors at NIF.",
"URL": "http://ui.adsabs.harvard.edu/abs/2012RScI...83jD312M/abstract",
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"Inertial confinement fusion",
"Physics",
"Neutron",
"Scintillator",
"Particle detector",
"Nuclear physics",
"Fusion power",
"National Ignition Facility",
"Deuterium",
"Neutron detection"
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"year_published": 2012,
"first_author": "Michael J. Moran",
"scholarly_citations_count": 7,
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"abstract": "Thin solid samples of deuteriumtritium DT have been seen to sublime and redistribute within spherical inertial fusion targets due to the heat generated by beta decay. We have frozen thin DT samples within glass shells of 890 and 3750 μm diameter, and observed the evolution of the solid towards more symmetric distributions using real time holographic interferometry. Holographic interferometry provides more sensitivity than direct imaging or classical interferometry to observe the thin 1030 μm solid samples in these shells.",
"title": "Holographic interferometry evidence that β-decay energy can symmetrize solid deuterium-tritium samples",
"URL": "https://www.osti.gov/scitech/biblio/7036217-holographic-interferometry-evidence-beta-decay-energy-can-symmetrize-solid-deuterium-tritium-samples",
"fields_of_study": [
"Analytical chemistry",
"Holographic interferometry",
"Fusion",
"Interferometry",
"Chemistry",
"Radioactive decay",
"Molecular physics",
"Sublimation (phase transition)",
"Deuterium",
"Tritium",
"Decay energy"
],
"year_published": 1990,
"first_author": "J. S. Ankney",
"scholarly_citations_count": 2,
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"abstract": "Low-temperature thermonuclear burn-up in deuterium-tritium mixtures with various deuteriumchar21tritiumchar21helium-3 ratios is considered. The general dependence is studied for the critical burn-up parameter upon the initial temperature T, density and tritium molar concentration for the mixture. In particular, it is shown that, if the tritium concentration decreases, then the critical burn-up parameter grows very quickly at fixed T and This means that tritium decay significantly complicates thermonuclear burn-up in deuterium-tritium mixtures.",
"title": "Influence of the tritium β - decay on low-temperature thermonuclear burn-up in deuterium-tritium mixtures",
"URL": "https://link.aps.org/doi/10.1103/PhysRevE.62.4104",
"fields_of_study": [
"Analytical chemistry",
"Physics",
"Nuclear physics",
"Deuterium",
"Tritium",
"Thermonuclear fusion"
],
"year_published": 2000,
"first_author": "Alexei M. Frolov",
"scholarly_citations_count": 6,
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{
"abstract": "We identify vapor-etched grain boundary grooves on the solid-vapor interface as the main source of surface roughness in the deuterium-tritium DT fuel layers, which are solidified and then cooled. Current inertial confinement fusion target designs impose stringent limits to the cross-sectional area and total volume of these grooves. Formation of these grain boundaries occurs over time scales of hours as the dislocation network anneals and is inevitable in a plastically deformed material. Therefore, either cooling on a much shorter time scale or a technique that requires no cooling after solidification should be used to minimize the roughness.",
"title": "Single crystal growth and formation of defects in deuterium-tritium layers for inertial confinement nuclear fusion",
"URL": "https://scitation.aip.org/content/aip/journal/apl/94/6/10.1063/1.3080655",
"fields_of_study": [
"Surface roughness",
"Inertial confinement fusion",
"Dislocation",
"Crystallographic defect",
"Materials science",
"Crystal growth",
"Grain boundary",
"Mechanics",
"Nuclear fusion",
"Surface finish",
"Crystallography"
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"year_published": 2009,
"first_author": "A. A. Chernov",
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"abstract": "Abstract In this study, the ignition criteria in the International Thermonuclear Experimental Reactor ITER associated with helium concentration is investigated. The main fuels used in this study are deuterium-tritium. Helium as the ash of deuterium-tritium reaction cannot be avoided. In this work, the effects of alpha particle concentration on plasma operation are investigated. The calculations were performed by using zero-dimensional power and particle balance equations. The results of our calculations show that the temporal evolution of alpha particle concentration becomes constant at 0.14. Then, ignition criteria and saddle points have been studied in τ E T, and P ht τ E 2 T planes for different alpha particle concentrations.",
"title": "Study of alpha particle concentration effects as the ash of deuterium-tritium fusion reaction on ignition criteria",
"URL": "NaN",
"fields_of_study": [
"Thermonuclear fusion",
"Materials science",
"Deuterium",
"Analytical Chemistry (journal)",
"Physics",
"Chemistry",
"Nuclear physics",
"Plasma",
"Chromatography"
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"year_published": 2022,
"first_author": "L Rajablou",
"scholarly_citations_count": 3,
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"sentence": "The main fuels used in this study are deuterium-tritium.",
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"sentence": "In this work, the effects of alpha particle concentration on plasma operation are investigated.",
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{
"abstract": "The RichtmyerMeshkov instability RMI at the ablation front of laser-irradiated planar targets is investigated by two-dimensional numerical hydrodynamics simulations. The linear evolution of perturbations seeded either by surface roughness or target inhomogeneity is studied for perturbation wavelengths in the range 10λ400 μm and laser intensity 41012I41014 Wcm2 with laser wavelength λlaser0.35 μm. Thin and thick cryogenic deuterium or deuterium-tritium DT planar targets are considered. For targets irradiated at constant intensity, it is found that perturbations with wavelength below a given threshold perform damped oscillations, while perturbations above such a threshold are unstable and oscillate with growing amplitude. This is qualitatively in agreement with theoretical predictions by Goncharov et al., according to which ablation related processes stabilize perturbations with kDc1, where Dc is the distance between the ablation front and critical density ...",
"title": "Numerical study of the ablative Richtmyer–Meshkov instability of laser-irradiated deuterium and deuterium-tritium targets",
"URL": "http://ui.adsabs.harvard.edu/abs/2010PhPl...17k2703M/abstract",
"fields_of_study": [
"Richtmyer–Meshkov instability",
"Physics",
"Atomic physics",
"Instability",
"Laser ablation",
"Rayleigh–Taylor instability",
"Laser",
"Deuterium",
"Wavelength",
"Plasma"
],
"year_published": 2010,
"first_author": "Alberto Marocchino",
"scholarly_citations_count": 17,
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]
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"entity": "deuterium"
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}
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{
"abstract": "Silicon carbide SiC detector is considered to be a good substitute for silicon Si detector in neutron detection, considering its mature of device fabrication in large sensitive area and thick sensitive volume, high charge-collection efficiency, significant neutrongamma discrimination, and excellent endurance in harsh environment, and it is expected to meet the demands of neutron detection in increasingly harsh irradiation field. The performance comparison between SiC and Si neutron detector in neutron irradiation is an important issue but is not fully studied no researcher has ever made a comparative study on them in constant fusion neutron irradiation. In this paper, the SiC and Si detectors irradiated by constant deuteriumtritium fusion neutron irradiation were tested and compared, getting significant difference in performance degradation a significant degradation was found in the Si detector at a neutron fluence of cm2, which showed a marked increase in dark current over four orders of magnitude and a serve reduction in the peak centroid of the alpha spectrum over 95, while nearly no degradation was observed in SiC detector at a much higher neutron fluence cm2. The SiC detector is proven to have better radiation resistance than the Si detector at a fluence of around cm2, and thus, it could replace the traditional Si detector in constant neutron irradiation field at least at a fluence of cm2.",
"title": "Performance Comparison Between SiC and Si Neutron Detectors in Deuterium–Tritium Fusion Neutron Irradiation",
"URL": "https://ieeexplore.ieee.org/stamp/stamp.jsp?tp=&arnumber=8653410",
"fields_of_study": [
"Irradiation",
"Neutron",
"Materials science",
"Fluence",
"Silicon carbide",
"Optoelectronics",
"Deuterium",
"Neutron flux",
"Neutron detection",
"Detector"
],
"year_published": 2019,
"first_author": "Linyue Liu",
"scholarly_citations_count": 19,
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"sentence": "The performance comparison between SiC and Si neutron detector in neutron irradiation is an important issue but is not fully studied no researcher has ever made a comparative study on them in constant fusion neutron irradiation.",
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"sentence": "In this paper, the SiC and Si detectors irradiated by constant deuteriumtritium fusion neutron irradiation were tested and compared, getting significant difference in performance degradation a significant degradation was found in the Si detector at a neutron fluence of cm2, which showed a marked increase in dark current over four orders of magnitude and a serve reduction in the peak centroid of the alpha spectrum over 95, while nearly no degradation was observed in SiC detector at a much higher neutron fluence cm2.",
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{
"abstract": "A magnetic recoil spectrometer MRS has been installed and extensively used on OMEGA and the National Ignition Facility NIF for measurements of the absolute neutron spectrum from inertial confinement fusion implosions. From the neutron spectrum measured with the MRS, many critical implosion parameters are determined including the primary DT neutron yield, the ion temperature, and the down-scattered neutron yield. As the MRS detection efficiency is determined from first principles, the absolute DT neutron yield is obtained without cross-calibration to other techniques. The MRS primary DT neutron measurements at OMEGA and the NIF are shown to be in excellent agreement with previously established yield diagnostics on OMEGA, and with the newly commissioned nuclear activation diagnostics on the NIF.",
"title": "Measuring the absolute deuterium-tritium neutron yield using the magnetic recoil spectrometer at OMEGA and the NIF.",
"URL": "https://www.ncbi.nlm.nih.gov/pubmed/23126915",
"fields_of_study": [
"Neutron scattering",
"Physics",
"Neutron",
"Neutron source",
"Neutron generator",
"Nuclear physics",
"Neutron temperature",
"Neutron spectroscopy",
"Neutron cross section",
"Neutron detection"
],
"year_published": 2012,
"first_author": "D. T. Casey",
"scholarly_citations_count": 36,
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{
"abstract": "Radiation survey meters and personal dosimeters are typically calibrated in reference neutron fields based on conventional radionuclide sources, such as americium-beryllium Am-Be or californium-252 Cf, either unmodified or heavy-water moderated. However, these calibration neutron fields differ significantly from the workplace fields in which most of these survey meters and dosimeters are being used. Although some detectors are designed to yield an approximately dose-equivalent response over a particular neutron energy range, the response of other detectors is highly dependent upon neutron energy. This, in turn, can result in significant over- or underestimation of the intensity of neutron radiation andor personal dose equivalent determined in the work environment. The use of simulated workplace neutron calibration fields that more closely match those present at the workplace could improve the accuracy of worker, and workplace, neutron dose assessment. This work provides an overview of the neutron fields found around nuclear power reactors and interim spent fuel storage installations based on available data. The feasibility of producing workplace-like calibration fields in an existing calibration facility has been investigated via Monte Carlo simulations. Several moderating assembly configurations, paired with a neutron generator using the deuterium tritium D-T fusion reaction, were explored.",
"title": "Investigation of Workplace-like Calibration Fields via a Deuterium-Tritium (D-T) Neutron Generator.",
"URL": "https://www.ncbi.nlm.nih.gov/pubmed/28234696",
"fields_of_study": [
"Nuclear engineering",
"Neutron",
"Calibration",
"Equivalent dose",
"Neutron generator",
"Materials science",
"Neutron temperature",
"Neutron radiation",
"Deuterium",
"Nuclear fusion"
],
"year_published": 2017,
"first_author": "Andrey V. Mozhayev",
"scholarly_citations_count": 3,
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"sentence": "Several moderating assembly configurations, paired with a neutron generator using the deuterium tritium D-T fusion reaction, were explored.",
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{
"abstract": "Diagnosing plasma magnetization in inertial confinement fusion implosions is important for understanding how magnetic fields affect implosion dynamics and to assess plasma conditions in magnetized implosion experiments. Secondary deuteriumtritium DT reactions provide two diagnostic signatures to infer neutron-averaged magnetization. Magnetically confining fusion tritons from deuteriumdeuterium DD reactions in the hot spot increases their path lengths and energy loss, leading to an increase in the secondary DT reaction yield. In addition, the distribution of magnetically confined DD-triton is anisotropic, and this drives anisotropy in the secondary DT neutron spectra along different lines of sight. Implosion parameter space as well as sensitivity to the applied B-field, fuel ρR, temperature, and hot-spot shape will be examined using Monte Carlo and 2D radiation-magnetohydrodynamic simulations.",
"title": "Diagnosing plasma magnetization in inertial confinement fusion implosions using secondary deuterium-tritium reactions.",
"URL": "https://aip.scitation.org/doi/10.1063/5.0043381",
"fields_of_study": [
"Inertial confinement fusion",
"Magnetic field",
"Nuclear physics",
"Materials science",
"Monte Carlo method",
"Implosion",
"Magnetization",
"Deuterium",
"Plasma",
"Anisotropy"
],
"year_published": 2021,
"first_author": "H. Sio",
"scholarly_citations_count": 14,
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"sentence": "Secondary deuteriumtritium DT reactions provide two diagnostic signatures to infer neutron-averaged magnetization.",
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"sentence": "In addition, the distribution of magnetically confined DD-triton is anisotropic, and this drives anisotropy in the secondary DT neutron spectra along different lines of sight.",
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{
"abstract": "A new class of ignition designs is proposed for inertial confinement fusion experiments. These designs are based on the hot-spot ignition approach, but instead of a conventional target that is comprised of a spherical shell with a thin frozen deuterium-tritium DT layer, a liquid DT sphere inside a wetted-foam shell is used, and the lower-density central region and higher-density shell are created dynamically by appropriately shaping the laser pulse. These offer several advantages, including simplicity in target production suitable for mass production for inertial fusion energy, absence of the fill tube leading to a more-symmetric implosion, and lower sensitivity to both laser imprint and physics uncertainty in shock interaction with the ice-vapor interface. The design evolution starts by launching an-Mbar shock into a DT sphere. After bouncing from the center, the reflected shock reaches the outer surface of the sphere and the shocked material starts to expand outward. Supporting ablation pressure ultimately stops such expansion and subsequently launches a shock toward the target center, compressing the ablator and fuel, and forming a shell. The shell is then accelerated and fuel is compressed by appropriately shaping the drive laser pulse, forming a hot spot using the conventional or shock ignition approaches. This Letter demonstrates the feasibility of the new concept using hydrodynamic simulations and discusses the advantages and disadvantages of the concept compared with more-traditional inertial confinement fusion designs.",
"title": "Novel Hot-Spot Ignition Designs for Inertial Confinement Fusion with Liquid-Deuterium-Tritium Spheres.",
"URL": "https://ui.adsabs.harvard.edu/abs/2020PhRvL.125f5001G/abstract",
"fields_of_study": [
"Inertial confinement fusion",
"Spherical shell",
"Ignition system",
"Materials science",
"Implosion",
"Fusion power",
"Shell (structure)",
"Laser",
"Mechanics",
"Shock (mechanics)"
],
"year_published": 2020,
"first_author": "V. N. Goncharov",
"scholarly_citations_count": 9,
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"sentence": "Supporting ablation pressure ultimately stops such expansion and subsequently launches a shock toward the target center, compressing the ablator and fuel, and forming a shell.",
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"entity": "shell"
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"sentence": "This Letter demonstrates the feasibility of the new concept using hydrodynamic simulations and discusses the advantages and disadvantages of the concept compared with more-traditional inertial confinement fusion designs.",
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}
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},
{
"abstract": "Calculations were performed for sup 238U and sup 232Th blankets for a fusion hybrid reactor. Comparisons between results using ENDFB-III and ENDFB-IV cross sections for sup 238U were made. Corrections to the latter cross-section set were suggested, bringing the computed results close to the reported experimental ones. Computations using ENDFB-IV sup 232Th cross sections were found to agree very well with experiment.",
"title": "Reaction Rate Calculations in Uranium and Thorium Blankets Surrounding a Central Deuterium-Tritium Neutron Source",
"URL": "http://www.osti.gov/scitech/biblio/6918605-reaction-rate-calculations-uranium-thorium-blankets-surrounding-central-deuterium-tritium-neutron-source",
"fields_of_study": [
"Isotopes of thorium",
"Inertial confinement fusion",
"Radiochemistry",
"Neutron source",
"Nuclear physics",
"Chemistry",
"Uranium-238",
"Thorium",
"Uranium",
"Deuterium",
"Isotopes of uranium"
],
"year_published": 1980,
"first_author": "A.D. Krumbein",
"scholarly_citations_count": 10,
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{
"abstract": "The present status of various deuterium-tritium D-T neutron sources is given, including the prospects for improvements. By upgrading a Rotating Target Neutron Source II-type neutron generator, a...",
"title": "High-lntensity 14-MeV Deuterium-Tritium Neutron Generators: Present Achievements and Future Potential",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/NSE90-A27472",
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"Neutron generator",
"Nuclear physics",
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"Tritium"
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"year_published": 1990,
"first_author": "G. Petö",
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"abstract": "Abstract The tritium aspects of the DT fuel cycle embody some of the most challenging feasibility and attractiveness issues in the development of fusion systems. The review and analyses in this paper provide important information to understand and quantify these challenges and to define the phase space of plasma physics and fusion technology parameters and features that must guide a serious RampD in the world fusion program. We focus in particular on components, issues and RampD necessary to satisfy three principal requirements 1 achieving tritium self-sufficiency within the fusion system, 2 providing a tritium inventory for the initial start-up of a fusion facility, and 3 managing the safety and biological hazards of tritium. A primary conclusion is that the physics and technology state-of-the-art will not enable DEMO and future power plants to satisfy these principal requirements. We quantify goals and define specific areas and ideas for physics and technology RampD to meet these requirements. A powerful fuel cycle dynamics model was developed to calculate time-dependent tritium inventories and flow rates in all parts and components of the fuel cycle for different ranges of parameters and physics and technology conditions. Dynamics modeling analyses show that the key parameters affecting tritium inventories, tritium start-up inventory, and tritium self-sufficiency are the tritium burn fraction in the plasma , fueling efficiency η , processing time of plasma exhaust in the inner fuel cycle , reactor availability factor AF, reserve time which determines the reserve tritium inventory needed in the storage system in order to keep the plant operational for time in case of any malfunction of any part of the tritium processing system, and the doubling time . Results show that η gt 2 and processing time of 14 are required to achieve tritium self-sufficiency with reasonable confidence. For η 2 and processing time of 4 , the tritium start-up inventory required for a 3 GW fusion reactor is 11 kg, while it is lt5 kg if η 5 and the processing time is 1 . To achieve these stringent requirements, a serious RampD program in physics and technology is necessary. The EU-DEMO direct internal recycling concept that carries fuel directly from the plasma exhaust gas to the fueling systems without going through the isotope separation system reduces the overall processing time and tritium inventories and has positive effects on the required tritium breeding ratio TBRR. A significant finding is the strong dependence of tritium self-sufficiency on the reactor availability factor. Simulations show that tritium self-sufficiency is impossible if AF lt 10 for any η , possible if AF gt 30 and 1 η 2, and achievable with reasonable confidence if AF gt 50 and η gt 2. These results are of particular concern in light of the low availability factor predicted for the near-term plasma-based experimental facilities .. FNSF, VNS, CTF, and can have repercussions on tritium economy in DEMO reactors as well, unless significant advancements in RAMI are made. There is a linear dependency between the tritium start-up inventory and the fusion power. The required tritium start-up inventory for a fusion facility of 100 MW fusion power is as small as 1 kg. Since fusion power plants will have large powers for better economics, it is important to maintain a reserve tritium inventory in the tritium storage system to continue to fuel the plasma and avoid plant shutdown in case of malfunctions of some parts of the tritium processing lines. But our results show that a reserve time as short as 24 leads to unacceptable reserve and start-up inventory requirements. Therefore, high reliability and fast maintainability of all components in the fuel cycle are necessary in order to avoid the need for storing reserve tritium inventory sufficient for continued fusion facility operation for more than a few hours. The physics aspects of plasma fueling, tritium burn fraction, and particle and power exhaust are highly interrelated and complex, and predictions for DEMO and power reactors are highly uncertain because of lack of experiments with burning plasma. Fueling by pellet injection on the high field side of tokamak has evolved to be the preferred method to fuel a burning plasma. Extrapolation from the DIII-D penetration scaling shows fueling efficiency expected in DEMO to be lt25, but such extrapolations are highly uncertain. The fueling efficiency of gas in a reactor relevant regime is expected to be extremely poor and not very useful for getting tritium into the core plasma efficiently. Gas fueling will nonetheless be useful for feedback control of the divertor operating parameters. Extensive modeling has been carried out to predict burn fraction, fueling requirements, and fueling efficiency for ITER, DEMO, and beyond. The fueling rate required to operate Q 10 ITER plasmas in order to provide the required core fueling, helium exhaust and radiative divertor plasma conditions for acceptable divertor power loads was calculated. If this fueling is performed with a 5050 DT mix, the tritium burn fraction in ITER would be 0.36, which is too low to satisfy the self-sufficiency conditions derived from the dynamics modeling for fusion reactors. Extrapolation to DEMO using this approach would also yield similarly low burn fraction. Extensive analysis presented shows that specific features of edge neutral dynamics in ITER and fusion reactors, which are different from present experiments, open possibilities for optimization of tritium fueling and thus to improve the burn fraction. Using only tritium in pellet fueling of the plasma core, and only deuterium for edge density, divertor power load and ELM control results in significant increase of the burn fraction to 1.83.6. These estimates are performed with physics models whose results cannot be fully validated for ITER and DEMO plasma conditions since these cannot be achieved in present tokamak experiments. Thus, several uncertainties remain regarding particle transport and scenario requirements in ITER and DEMO. The safety standard requirements for protection of the public and release guidelines for tritium have been reviewed. General safety approaches including minimizing tritium inventories, reducing tritium permeation through materials, and decontaminating material for waste disposal have been suggested.",
"title": "Physics and technology considerations for the deuterium–tritium fuel cycle and conditions for tritium fuel self sufficiency",
"URL": "http://ui.adsabs.harvard.edu/abs/2021NucFu..61a3001A/abstract",
"fields_of_study": [
"Nuclear engineering",
"Physics",
"Fuel cycle",
"Deuterium",
"Tritium"
],
"year_published": 2020,
"first_author": "Mohamed A. Abdou",
"scholarly_citations_count": 64,
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"abstract": "The National Ignition Facility has been used to compress deuterium-tritium to an average areal density of 1.00.1 cm-2, which is 67 of the ignition requirement. These conditions were obtained using 192 laser beams with total energy of 1-1.6 MJ and peak power up to 420 TW to create a hohlraum drive with a shaped power profile, peaking at a soft -ray radiation temperature of 275-300 eV. This pulse delivered a series of shocks that compressed a capsule containing cryogenic deuterium-tritium to a radius of 25-35 μm. Neutron images of the implosion were used to estimate a fuel density of 500-800 cm-3.",
"title": "Assembly of high-areal-density deuterium-tritium fuel from indirectly driven cryogenic implosions.",
"URL": "http://ui.adsabs.harvard.edu/abs/2012PhRvL.108u5005M/abstract",
"fields_of_study": [
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"Neutron",
"Ignition system",
"Area density",
"Materials science",
"Implosion",
"National Ignition Facility",
"Hohlraum",
"Deuterium",
"Radius"
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"year_published": 2012,
"first_author": "A. J. MacKinnon",
"scholarly_citations_count": 60,
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"sentence": "These conditions were obtained using 192 laser beams with total energy of 1-1.6 MJ and peak power up to 420 TW to create a hohlraum drive with a shaped power profile, peaking at a soft -ray radiation temperature of 275-300 eV. This pulse delivered a series of shocks that compressed a capsule containing cryogenic deuterium-tritium to a radius of 25-35 μm.",
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"entity": "Inertial Confinement Fusion"
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"entity": "Radiation temperature"
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"sentence": "Neutron images of the implosion were used to estimate a fuel density of 500-800 cm-3.",
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"category": "Detection and Monitoring Systems",
"entity": "Neutron images"
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{
"abstract": "The dispersion relation and damping rate of kinetic Alfvén waves KAWs in a deuterium-tritium fusion plasma with slowing-down distributed α-particles are investigated using the kinetic theory. The variations of wave frequency and damping rate with respect to the α concentration nα and perpendicular wave number are studied from a numerical way. The results show that the fluctuation of α concentration slightly affects the frequency and damping rate of KAWs at low nα . In addition, the frequency and the damping rate increase as the and the background temperature T increase. For comparison, the calculations are performed also in the case of α-particles following an equivalent Maxwellian distribution. For a given , the value of the frequency obtained in the slowing-down distribution case is smaller than that obtained in the Maxwellian distribution case. Conversely, the value of the damping rate obtained in the slowing-down distribution case is slightly larger than that obtained in the Maxwellian distribution case.",
"title": "Kinetic Alfvén waves in a deuterium-tritium fusion plasma with slowing-down distributed α-particles",
"URL": "https://iopscience.iop.org/article/10.1088/1674-1056/ac2d18",
"fields_of_study": [
"Kinetic energy",
"Radiochemistry",
"Materials science",
"Fusion plasma",
"α particles",
"Deuterium",
"Tritium"
],
"year_published": 2022,
"first_author": "Fei-Fei Lu",
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{
"abstract": "Inclusion of inverse Compton effects in the calculation of deuterium-deuterium burn under the extreme conditions considered by Eliezer et al. are shown to decrease the maximum burn temperature from about 300 keV to only 100--150 keV. This decrease is such that tritium breeding by the DD-- T reaction is not sufficient to replace the small amount of tritium that is initially added to the deuterium plasma in order to trigger ignition at less than 10 keV.",
"title": "Comment on \"Deuterium--tritium fusion reactors without external fusion breeding\" by Eliezer et al",
"URL": "https://arxiv.org/abs/physics/0201004v1",
"fields_of_study": [
"Fusion",
"Ignition system",
"Nuclear physics",
"Materials science",
"Fusion power",
"Deuterium plasma",
"Deuterium",
"Tritium",
"Physics",
"Lawson criterion",
"Atomic physics"
],
"year_published": 1999,
"first_author": "Andre Gsponer",
"scholarly_citations_count": 7,
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"abstract": "Abstract A deuteriumtritium DT nuclear pulse propulsion concept for fast interplanetary transport is proposed utilizing almost all the energy for thrust and without the need for a large radiator 1. By letting the thermonuclear micro-explosion take place in the center of a liquid hydrogen sphere with the radius of the sphere large enough to slow down and absorb the neutrons of the DT fusion reaction, heating the hydrogen to a fully ionized plasma at a temperature of 105 K. 2. By using the entire spacecraft as a magnetically insulated gigavolt capacitor, igniting the DT micro-explosion with an intense GeV ion beam discharging the gigavolt capacitor, possible if the space craft has the topology of a torus.",
"title": "Deuterium–tritium pulse propulsion with hydrogen as propellant and the entire space-craft as a gigavolt capacitor for ignition",
"URL": "https://arxiv.org/pdf/1211.5987.pdf",
"fields_of_study": [
"Nuclear engineering",
"Electrical engineering",
"Physics",
"Ignition system",
"Nuclear pulse propulsion",
"Liquid hydrogen",
"Hydrogen",
"Deuterium",
"Nuclear fusion",
"Thermonuclear fusion",
"Propellant"
],
"year_published": 2013,
"first_author": "Friedwardt Winterberg",
"scholarly_citations_count": 5,
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"sentence": "By using the entire spacecraft as a magnetically insulated gigavolt capacitor, igniting the DT micro-explosion with an intense GeV ion beam discharging the gigavolt capacitor, possible if the space craft has the topology of a torus.",
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"entity": "torus"
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"entity": "GeV ion beam"
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"abstract": "Linear and non-linear models for anomalous alpha particle transport due to collective instabilities are reviewed. The linear stability analysis is applied to the comparison of measured and computed Alfvn eigenmodes in tokamaks spectroscopy. Scenarios for non-linear wave evolution and fast ion redistribution are discussed.",
"title": "Theory of alfvén eigenmode instabilities and related alpha particle transport in JET deuterium-tritium plasmas",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/38/9/305",
"fields_of_study": [
"Tokamak",
"Physics",
"Ion",
"Magnetic confinement fusion",
"Nuclear physics",
"Instability",
"Magnetohydrodynamics",
"Charged particle",
"Alpha particle",
"Plasma"
],
"year_published": 1998,
"first_author": "Wolfgang Kerner",
"scholarly_citations_count": 33,
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"sentence": "The linear stability analysis is applied to the comparison of measured and computed Alfvn eigenmodes in tokamaks spectroscopy.",
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{
"abstract": "Abstract The nuclear reaction of deuteriumtritium DT fusion by the usual magnetic or inertial confinement suffers from a number of difficulties and problems caused by tritium handling, neutron damage to materials and neutron-induced radioactivity, etc. The study of the nuclear synthesis reaction of deuteriumhelium-3 D3He at low collision energies below 1 keV is of interest for its applications in nuclear physics and astrophysics. Spherical tokamak ST reactors have a low aspect ratio and can confine plasma with β1. These capabilities of ST reactors are due to the use of the alternative D3He reaction. In this work, the burn condition of D3He reaction was calculated by using zero-dimensional particles and power equations, and, with the use of the parameters of the ST reactor, the stability limit of D3He reaction was calculated and then the results were compared with those of DT reaction. The obtained results show that the burn conditions of D3He reaction required a higher temperature and had a much more limited temperature range in comparison to those of DT reaction.",
"title": "A Comparison Between the Burn Condition of Deuterium–Tritium and Deuterium–Helium-3 Reaction and Stability Limits",
"URL": "http://ui.adsabs.harvard.edu/abs/2015ZNatA..70...79M/abstract",
"fields_of_study": [
"Radiochemistry",
"Experimental physics",
"Materials science",
"Helium-3",
"Deuterium",
"Tritium"
],
"year_published": 2015,
"first_author": "S. M. Motevalli",
"scholarly_citations_count": 11,
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{
"abstract": "The persistence of spin-polarized fuels is a crucial problem for polarized magnetic and inertial confinement fusion ICF. The depolarizations of polarized deuterium-tritium DT fuels in indirectly driven ICF implosions are investigated with three-dimensional spin transport hydrodynamics simulations. The spin transport equations for deuterons and tritons are derived with the density matrix formalism, which are used to investigate the evolutions of spin eigenstate distributions of DT fuel. The depolarization of DT ions by strong self-generated magnetic fields and the mixings of DT ions with different spin states can be captured by the spin transport equation. The simulation results show that triton polarizations are sensitive to large scale magnetic fields generated by polar mode asymmetries. It is also found that the depolarization of tritons can be reduced by an optimized spin alignment of the polarized fuel. The methods and results can be used to optimize the design of polarized fusion targets and interpret polarized fusion experiments.",
"title": "Numerical study of spin-polarized deuterium-tritium fuel persistence in inertial confinement fusion implosions",
"URL": "http://link.aps.org/pdf/10.1103/PhysRevResearch.5.033115",
"fields_of_study": [
"Deuterium",
"Inertial confinement fusion",
"Physics",
"Spin (aerodynamics)",
"Nuclear physics",
"Magnetic confinement fusion",
"Ion",
"Nuclear fusion",
"Depolarization",
"Atomic physics",
"Tritium",
"Plasma",
"Condensed matter physics",
"Tokamak",
"Quantum mechanics",
"Medicine",
"Thermodynamics",
"Endocrinology"
],
"year_published": 2023,
"first_author": "Ronghao Hu",
"scholarly_citations_count": "NaN",
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"sentence": "The depolarizations of polarized deuterium-tritium DT fuels in indirectly driven ICF implosions are investigated with three-dimensional spin transport hydrodynamics simulations.",
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"entity": "indirectly driven ICF implosions"
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{
"category": "Chemical Element or Compound",
"entity": "DT fuels"
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"category": "Software and simulation",
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}
]
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{
"sentence": "The spin transport equations for deuterons and tritons are derived with the density matrix formalism, which are used to investigate the evolutions of spin eigenstate distributions of DT fuel.",
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"category": "Particle",
"entity": "deuterons"
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"category": "Particle",
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},
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"entity": "DT fuel"
},
{
"category": "Plasma dynamic and behavior",
"entity": "spin transport"
},
{
"category": "Theory and Calculation",
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}
]
},
{
"sentence": "The depolarization of DT ions by strong self-generated magnetic fields and the mixings of DT ions with different spin states can be captured by the spin transport equation.",
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"category": "Particle",
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"entity": "depolarization"
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"category": "Field Configuration",
"entity": "strong self-generated magnetic fields"
},
{
"category": "Plasma dynamic and behavior",
"entity": "mixings of DT ions with different spin states"
},
{
"category": "Theory and Calculation",
"entity": "spin transport equation"
}
]
},
{
"sentence": "The methods and results can be used to optimize the design of polarized fusion targets and interpret polarized fusion experiments.",
"entities": [
{
"category": "Nuclear Fusion System Component",
"entity": "polarized fusion targets"
},
{
"category": "Experimental Apparatus",
"entity": "polarized fusion experiments"
},
{
"category": "Concept",
"entity": "polarized fusion"
}
]
}
]
},
{
"abstract": "Planned experiments in the Joint European Torus JET with deuterium-tritium D-T plasmas require high fusion performance for alpha-particle heating studies and for investigation of isotope dependence in conditions relevant to the International Thermonuclear Experimental Reactor. In deuterium plasmas, the highest neutron rates have been obtained in the hot-ion high-confinement mode H mode which is ultimately limited by magnetohydrodynamic MHD phenomena when the pressure gradient approaches ideal ballooning and kink stability limits in the vicinity of the edge transport barrier. Results are reported confirming the MkII divertors increased closure and pumping in this regime, progress in understanding the MHD-related termination is discussed, and the use of ion cyclotron resonance heating ICRH in combination with high-power neutral beams to increase the neutron yield is described. In separate experiments internal transport barriers have been established through careful programming of the current ramp and heating waveforms, and neutron emission comparable with the best hot-ion II-modes achieved. Steady-state II-mode discharges exhibiting edge localized modes ELMs in reactor-like configurations and conditions have been demonstrated, including cases in which relevant dimensionless parameter values are preserved, ready also for testing in D-T. C 1997 American institute of Physics.",
"title": "High performance Joint European Torus (JET) plasmas for deuterium–tritium operation with the MkII divertor",
"URL": "https://infoscience.epfl.ch/record/119558",
"fields_of_study": [
"Physics",
"Neutron",
"Neutron emission",
"Nuclear physics",
"Joint European Torus",
"Divertor",
"Magnetohydrodynamics",
"Deuterium",
"Thermonuclear fusion",
"Plasma"
],
"year_published": 1997,
"first_author": "T. T. C. Jones",
"scholarly_citations_count": 12,
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"category": "Particle",
"entity": "alpha-particle"
},
{
"category": "Chemical Element or Compound",
"entity": "deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "tritium"
},
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"category": "Plasma property",
"entity": "D-T plasmas"
}
]
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{
"sentence": "In deuterium plasmas, the highest neutron rates have been obtained in the hot-ion high-confinement mode H mode which is ultimately limited by magnetohydrodynamic MHD phenomena when the pressure gradient approaches ideal ballooning and kink stability limits in the vicinity of the edge transport barrier.",
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"category": "Particle",
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{
"sentence": "Results are reported confirming the MkII divertors increased closure and pumping in this regime, progress in understanding the MHD-related termination is discussed, and the use of ion cyclotron resonance heating ICRH in combination with high-power neutral beams to increase the neutron yield is described.",
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"category": "Nuclear Fusion System Component",
"entity": "MkII divertors"
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{
"sentence": "In separate experiments internal transport barriers have been established through careful programming of the current ramp and heating waveforms, and neutron emission comparable with the best hot-ion II-modes achieved.",
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"entity": "H-mode"
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"entity": "internal transport barriers"
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{
"category": "Experimental Apparatus",
"entity": "heating waveforms"
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"category": "Detection and Monitoring Systems",
"entity": "neutron emission"
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"category": "Plasma dynamic and behavior",
"entity": "plasma transport"
}
]
},
{
"sentence": "Steady-state II-mode discharges exhibiting edge localized modes ELMs in reactor-like configurations and conditions have been demonstrated, including cases in which relevant dimensionless parameter values are preserved, ready also for testing in D-T. C 1997 American institute of Physics.",
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{
"abstract": "Since the tokamak scheme of plasma confinement provides a toroidal source of fusion neutrons, wide variations in the source distribution at the wall surface are possible. A numerical solution of the neutron streaming equation has been applied to the calculation of the flux and current as functions of wall position for a circular cross-section tokamak and two noncircular tokamaks, the Princeton Reference Design PRD and the University of Wisconsin UWMAK-I. The results show significant variations in the pattern of the angular flux and substantial peaking in the scalar flux and current. For example, the current peaks at 22 percent above nominal for the circular case, 43 percent for the PRD, and 12 percent for UWMAK-I. The nominal value, total sourcetotal area, is the commonly stated wall load. Effects of this magnitude cannot be ignored in future reactor designs when power densities, damage rates, etc., are evaluated.",
"title": "A comparison of the deuterium-tritium neutron wall load distributions in several Tokamak fusion reactor designs",
"URL": "https://ui.adsabs.harvard.edu/abs/1976NucTe..31...32C/abstract",
"fields_of_study": [
"Tokamak",
"Physics",
"Toroid",
"Neutron",
"Nuclear physics",
"Flux",
"Mechanics",
"Deuterium",
"Radiation flux",
"Neutron flux",
"Plasma"
],
"year_published": 1976,
"first_author": "David L. Chapin",
"scholarly_citations_count": 7,
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"abstract": "The linear instabilities and nonlinear transport driven by the ion temperature gradient ITG instability are numerically investigated in deuteriumtritium plasma in the CFETR hybrid scenario by using the NLT code. In both linear and nonlinear simulations, effects of the tritium fraction ɛT and the temperature ratio of deuterium and tritium τDT TDTT are studied, with TD and TT being the temperature of deuterium and tritium, respectively. Results from linear simulations illustrate that the ITG instability can be well stabilized as ɛT increases. When ɛT 0.5, the maximum growth rate occurs at around τDT 1.5. During the nonlinear simulations, the anomalous particle and energy flux in deuteriumtritium plasma are analyzed. For τDT 1.0, it is found that the tritium deuterium particle flux is inward outward and the largest inward tritium particle flux appears at ɛT 0.5. The total ion energy flux is found to be insensitive to ɛT. In the case with ɛT 0.5, as τDT decreases from 3.0 to 0.5, the particle flux for tritium deuterium changes from the outward inward direction to the inward outward direction. The quasilinear analysis clarifies that the particle flux driven by the temperature gradient is the key part in determining the direction of the particle flux. Besides, the largest and the smallest energy flux appear at around τDT 1.5 and 0.5, respectively. It is indicated that better energy confinement and better particle confinement for tritium could be realized by choosing smaller τDT or higher TT.",
"title": "Gyrokinetic simulations of ion temperature gradient instability in deuterium–tritium plasma in the CFETR hybrid scenario",
"URL": "https://pubs.aip.org/aip/adv/article-pdf/doi/10.1063/5.0155150/18121059/095312_1_5.0155150.pdf",
"fields_of_study": [
"Tritium",
"Deuterium",
"Flux (metallurgy)",
"Plasma",
"Ion",
"Particle (ecology)",
"Atomic physics",
"Instability",
"Nuclear physics",
"Physics",
"Chemistry",
"Mechanics",
"Oceanography",
"Organic chemistry",
"Quantum mechanics",
"Geology"
],
"year_published": 2023,
"first_author": "Ruzhi Tang",
"scholarly_citations_count": "NaN",
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"sentence": "For τDT 1.0, it is found that the tritium deuterium particle flux is inward outward and the largest inward tritium particle flux appears at ɛT 0.5.",
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{
"abstract": "An accurate understanding of burn dynamics in implosions of cryogenically layered deuterium D and tritium T filled capsules, obtained partly through precision diagnosis of these experiments, is essential for assessing the impediments to achieving ignition at the National Ignition Facility. We present measurements of neutrons from such implosions. The apparent ion temperatures T_ are inferred from the variance of the primary neutron spectrum. Consistently higher DT than DD T_ are observed and the difference is seen to increase with increasing apparent DT T_. The line-of-sight rms variations of both DD and DT T_ are small, 150eV, indicating an isotropic source. The DD neutron yields are consistently high relative to the DT neutron yields given the observed T_. Spatial and temporal variations of the DT temperature and density, DD-DT differential attenuation in the surrounding DT fuel, and fluid motion variations contribute to a DT T_ greater than the DD T_, but are in a one-dimensional model insufficient to explain the data. We hypothesize that in a three-dimensional interpretation, these effects combined could explain the results.",
"title": "Indications of flow near maximum compression in layered deuterium-tritium implosions at the National Ignition Facility",
"URL": "https://link.aps.org/doi/10.1103/PhysRevE.94.021202",
"fields_of_study": [
"Ion",
"Neutron",
"Ignition system",
"Isotropy",
"Attenuation",
"Atomic physics",
"Materials science",
"National Ignition Facility",
"Deuterium",
"Tritium"
],
"year_published": 2016,
"first_author": "M. Gatu Johnson",
"scholarly_citations_count": 54,
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"entity": "Capsules"
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"entity": "Implosions"
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"entity": "Burn dynamics"
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{
"category": "Detection and Monitoring Systems",
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{
"abstract": "A numerical procedure for calculating the equilibrium thickness distribution of a thin layer of deuterium and tritium on the inner surface of an indirect drive target sphere 2.0 mm in diameter is described. Starting with an assumed uniform thickness layer and with specified thermal boundary conditions, the temperature distribution throughout the capsule and hohlraum including natural convection in the hohlraum gas is calculated. Results are used to make a first estimate of the final non-uniform thickness distribution of the layer. This thickness distribution is then used to make a second calculation of the temperature distribution with the same boundary conditions. Legendre polynomial coefficients are evaluated for the two temperature distributions and the two thickness profiles. Final equilibrium Legendre coefficients are determined by linear extrapolation. From these coefficients, the equilibrium layer thickness can be computed.",
"title": "Predicting the Equilibrium Deuterium-Tritium Fuel Layer Thickness Profile in an Indirect-Drive Hohlraum Capsule",
"URL": "http://www.osti.gov/scitech/servlets/purl/15005466",
"fields_of_study": [
"Inertial confinement fusion",
"Legendre polynomials",
"Extrapolation",
"Boundary layer thickness",
"Boundary value problem",
"Atomic physics",
"Materials science",
"Hohlraum",
"Natural convection",
"Mechanics",
"Deuterium"
],
"year_published": 2004,
"first_author": "J. J. Sanchez",
"scholarly_citations_count": 14,
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{
"abstract": "The levels of induced activity in samples of ITER materials and dosimetry foils to be irradiated during the planned JET campaign with deuterium-tritium D-T plasma were predicted. Calculations were performed for the neutron energy spectrum of the JET internal Long Term Irradiation Station LTIS. The European Activation System EASY-II and the EAF-2010 nuclear data library were used in order to estimate specific activity and dose rates as a function of time after the end of irradiation. The results of the study provide important data for comparison against activation measurements and support the planning of the irradiation, measurement and radiation protection procedures to be implemented in the planned JET activation experiment.",
"title": "Preparation of activation experiments for ITER material characterization and data validation in the Deuterium–Tritium JET campaign",
"URL": "https://eproceedings.epublishing.ekt.gr/index.php/hnps/article/view/1844",
"fields_of_study": [
"Irradiation",
"Nuclear engineering",
"Jet (fluid)",
"Materials science",
"Radiation protection",
"Nuclear data",
"Deuterium",
"Tritium",
"Dosimetry",
"Plasma"
],
"year_published": 2019,
"first_author": "T. Vasilopoulou",
"scholarly_citations_count": "NaN",
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"abstract": "Tritiumless blanket designs, associated with a catalyzed deuterium-deuterium D-D fusion cycle and using a single high temperature solid pebble or falling bed zone, for process heat production, ar...",
"title": "CATALYZED DEUTERIUM-DEUTERIUM AND DEUTERIUM-TRITIUM FUSION BLANKETS FOR HIGH TEMPERATURE PROCESS HEAT PRODUCTION.",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST82-A20734",
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"abstract": "The technological exploitation of the deuteriumtritium campaign at JET is the objective of the EUROfusion work package JET3 and, through the NEXP subproject, it intends to take advantage of the expected significant neutron production to validate the numerical tools used for shutdown dose rate SDR assessment and to study the reasons of discrepancies between calculations and measurements. The tritium campaign C40 was held in the first half of 2021 and two active gamma dosimeters based on spherical 1-L air-vented ionization chambers ICs were installed in some ex-vessel positions close to the horizontal ports of the tokamak in octants 1 and 2, have been employed to measure the dose rate. Moreover, for the deuteriumtritium campaign C41 DTE2, a third IC suitable for higher dose rates was installed in octant 1. The present work is dedicated to the analysis of dose rate measurements carried out during the tritium campaign during the inter-pulse periods and the shutdown. Influence quantities and error sources are analyzed in order to calculate the dose rate from the raw signal and experimental uncertainty. Some improvements in the experimental equipment are described as well, as the assessment of the sensitivity of the ICs to the variation of oxygen concentration in the air to simulate the nitrogen-enriched atmosphere in the JET torus hall during tritium operation and the upgrade of the acquisition software to interface it with CODAS data store.",
"title": "Dose Rate Measurements During the Tritium Campaign at JET and Diagnostic Improvements for the Deuterium–Tritium Experiments",
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"abstract": "The performance of triple-picket deuterium-tritium cryogenic target designs on the OMEGA Laser System is reported. These designs facilitate control of shock heating in low-adiabat inertial confinement fusion targets. Areal densities up to 300 mgcm2 the highest ever measured in cryogenic deuterium-tritium implosions are inferred in the experiments with an implosion velocity approximately 3x107 cms driven at peak laser intensities of 8x1014 Wcm2. Extension of these designs to ignition on the National Ignition Facility is presented.",
"title": "Demonstration of the highest deuterium-tritium areal density using multiple-picket cryogenic designs on OMEGA.",
"URL": "https://europepmc.org/article/MED/20482056",
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"Ignition system",
"Cryogenics",
"Nuclear physics",
"Implosion",
"National Ignition Facility",
"Omega",
"Laser",
"Deuterium"
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"year_published": 2010,
"first_author": "Valeri Goncharov",
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"abstract": "A simple model is presented to calculate the fusion yield from the fast heating of compressed deuteriumtritium DT. The model is applicable when the fusion yield is small enough to neglect self-heating. Since 80 of the fusion yield escapes as 14 MeV neutrons, self-heating is small as long as the fusion yield is less than the deposited energy, .., the fusion gain, Q1. We show the model is in good agreement with detailed numerical simulations when this condition is satisfied, as will be the case for fast ignition experiments in the near future. The model is used to calculate the fast heating fusion yields as a function of the important parameters such as the fuel density, deposited energy, and pulse length. The model is also used to obtain the minimum energy, Eq1, and the fuel diameter, , necessary to obtain Q1, which is given approximately by the scaling laws Eq115.3ρ1001.5 kJ, and d16.5ρ1000.84 μm, where ρ is the DT density. These scaling laws should help the design of Q1 experiments.",
"title": "Subignition fusion yields generated by fast heating of compressed deuterium–tritium and break-even scaling",
"URL": "https://scitation.aip.org/content/aip/journal/pop/11/7/10.1063/1.1753574",
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"Fusion ignition",
"Neutron",
"Fusion",
"Lawson criterion",
"Nuclear physics",
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"Yield (chemistry)",
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"first_author": "S. A. Slutz",
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"abstract": "Two natural diamond detectors NDDs operating at room temperature were used for Fusion Neutronics Source FNS deuteriumtritium DT neutron spectra measurements at different points around the tritium target and for different deuteron beam energies. Energy resolution of both NDDs were measured, with values 1.95 and 2.8. Due to the higher energy resolution of one of the two NDDs studied it was possible to measure the shape of the DT neutron energy distribution and its broadening due to deuteron scattering inside the target. The influence of pulse pileup on the energy resolution of the combined system NDDelectronics at count rates up to 3.8105 countss was investigated. A 3.58 energy resolution for the spectrometric system based on NDD and a 0.25 μs shaping time amplifier has been measured at a count rate of 5.7105 countss. It is shown that special development of a fast pulse signal processor is necessary for NDD based spectrometry at count rates of approximately 106 countss.",
"title": "Fusion Neutronic Source deuterium–tritium neutron spectrum measurements using natural diamond detectors",
"URL": "https://aip.scitation.org/doi/10.1063/1.1148001",
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"Semiconductor detector",
"Neutron",
"Neutron source",
"Nuclear physics",
"Neutron temperature",
"Neutron spectroscopy",
"Plasma diagnostics",
"Deuterium",
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"year_published": 1997,
"first_author": "A. V. Krasilnikov",
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"abstract": "AbstractThe recent deuteriumtritium campaign in JET-ILW DTE2 has provided a unique opportunity to study the isotope dependence of the L-H power threshold in an ITER-like wall environment Be wall and W divertor. Here we present results from dedicated L-H transition experiments at JET-ILW, documenting the power threshold in tritium and deuteriumtritium plasmas, comparing them with the matching deuterium and hydrogen datasets. From earlier experiments in JET-ILW it is known that as plasma isotopic composition changes from deuterium, through varying deuteriumhydrogen concentrations, to pure hydrogen, the value of the line averaged density at which the threshold is minimum,nˉe,min, increases, leading us to expect thatnˉe,minT ltnˉe,minDT ltnˉe,minD ltnˉe,minH. The new power threshold data confirms these expectations in most cases, with the corresponding ordering of the minimum power thresholds. We present a comparison of this data to power threshold scalings, used for extrapolation to future devices such as ITER and DEMO.",
"title": "L-H transition studies in tritium and deuterium–tritium campaigns at JET with Be wall and W divertor",
"URL": "https://iopscience.iop.org/article/10.1088/1741-4326/acee12/pdf",
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"Physics",
"Atomic physics",
"Plasma",
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"sentence": "We present a comparison of this data to power threshold scalings, used for extrapolation to future devices such as ITER and DEMO.",
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"category": "Nuclear Fusion Experimental Facility",
"entity": "ITER"
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{
"abstract": "x0D x0D x0D Fusion reaction simulation of two types of nucleon proton and neutron, is reported in this paper. The interactions between these nucleons are assumed to be only the nuclear force and electrostatic. The modeling is done in a classical approach where molecules formed by the nucleons are being collided with each other. In the model, some parameters were configured to see how these parameters affect the simulation. Some interesting results is that we can find a stable Helium-5 and a neutron-neutron pair as the product of the collision which should not have been possible due to the the quark interactions inside them. This leads us to a conclusion that we need to add a force-model for quark interaction. We do this by using an electrostatic-like force. However using this model, we may end up to instability of the tritium. In this paper we also report a configuration where the neutron-pair is unstable while tritium is stable.x0D x0D x0D",
"title": "Classical Approach for the Fusion Reaction of Deuterium-Tritium Using 2-D Velocity Verlet Method",
"URL": "NaN",
"fields_of_study": "NaN",
"year_published": 2015,
"first_author": "Dani Irawan",
"scholarly_citations_count": "NaN",
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{
"abstract": "The state of burning plasma had been achieved in inertial confinement fusion ICF, which was regarded as a great milestone for high-gain laser fusion energy. In the burning plasma, alpha particles incident on the cryogenic warm dense fuels cannot be simply regarded as single particles, and the new physics brought about by the density effects of alpha particles should be considered. In this work, the collective interaction between them has been considered, namely, the effect of the superposition of wake waves. The stopping power of alpha-particle clusters, .., the rate of energy loss per unit distance traveled has been calculated using both analytical and simulation approaches. In theory, we obtain the stopping power of alpha clusters in cryogenic warm dense fuel by the dielectric function method, which illustrates the importance of the effective interaction between particles. Simulation results using the LAPINS code show that the collective stopping power of the alpha cluster is indeed increased via coherent superposition of excitation fields the excitation of high-amplitude wake waves. However, the comparison between simulation and theoretical results also illustrates a coherentdecoherent transition of the stopping power of the cluster. The initial conditions with various sizes and densities of the alpha clusters have been considered to verify the condition of decoherence transition. Our work provides a theoretical description of the transport properties of high-density alpha particles in warm dense cryogenic fuel and might give some theoretical guidance for the design of actual fusion processes.",
"title": "Stopping power of high-density alpha-particle clusters in partially degenerated deuterium–tritium fuels",
"URL": "https://arxiv.org/pdf/2304.14086",
"fields_of_study": [
"Physics",
"Deuterium",
"Tritium",
"Alpha particle",
"Nuclear physics",
"Alpha (finance)",
"Plasma",
"Atomic physics",
"Particle (ecology)",
"Medicine",
"Construct validity",
"Oceanography",
"Nursing",
"Patient satisfaction",
"Geology"
],
"year_published": 2023,
"first_author": "Z. P. Fu",
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"category": "Particle",
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"entity": "coherent superposition of excitation fields"
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"category": "Physical Process",
"entity": "excitation of high-amplitude wake waves"
}
]
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"sentence": "However, the comparison between simulation and theoretical results also illustrates a coherentdecoherent transition of the stopping power of the cluster.",
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"sentence": "The initial conditions with various sizes and densities of the alpha clusters have been considered to verify the condition of decoherence transition.",
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"sentence": "Our work provides a theoretical description of the transport properties of high-density alpha particles in warm dense cryogenic fuel and might give some theoretical guidance for the design of actual fusion processes.",
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"category": "Theory and Calculation",
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]
},
{
"abstract": "The neutron source characteristics of the Japan Atomic Energy Research Institute JAERIU.S. Department of Energy collaborative program on fusion neutronics Phase-IIA and-IIB experiments are dete...",
"title": "Characteristics of a Deuterium-Tritium Fusion Source on a Rotating Target Used in Simulated Fusion Blanket Experiments",
"URL": "https://www.ans.org/pubs/journals/fst/a_30400",
"fields_of_study": [
"Fusion",
"Neutron source",
"Nuclear physics",
"Materials science",
"Blanket",
"Neutron spectra",
"Fusion neutronics",
"Deuterium",
"Tritium",
"Neutron transport"
],
"year_published": 1995,
"first_author": "Masayuki Nakagawa",
"scholarly_citations_count": 5,
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"category": "Country and location",
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},
{
"abstract": "The results are given of time-of-flight measurements of the spectrum of neutrons generated by spherical heating of a CD2n target by the radiation of a nine-channel laser unit. It is reported that neutrons corresponding to the reaction Dt, nHe4 are generated in the laser plasma. A method is suggested for the determination of the degree of compression of the plasma from the numbers of the DT and DD neutrons formed in the plasma.",
"title": "Generation of deuterium-tritium neutrons by spherical heating of a solid target with high-power laser radiation",
"URL": "http://iopscience.iop.org/article/10.1070/QE1975v004n09ABEH011577/pdf",
"fields_of_study": [
"Inertial confinement fusion",
"Neutron",
"Radiation",
"Atomic physics",
"Materials science",
"Laser",
"Deuterium",
"Tritium",
"Dense plasma focus",
"Plasma"
],
"year_published": 1975,
"first_author": "N. G. Basov",
"scholarly_citations_count": 11,
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]
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"sentence": "A method is suggested for the determination of the degree of compression of the plasma from the numbers of the DT and DD neutrons formed in the plasma.",
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"entity": "plasma"
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]
}
]
},
{
"abstract": "An accurate equation of state for deuterium-tritium mixture is of crucial importance in inertial confinement fusion. The equation of state can determine the compressibility of the imploding target and the energy deposited into the fusion fuel. In the present work, a new deuterium-tritium equation of state, which is calculated according to quantum molecular dynamic and orbital free molecular dynamic simulations, has been used to study the target implosion hydrodynamics. The results indicate that the peak density predicted by the new equation of state is 10 higher than the quotidian equation of state data. During the implosion, the areal density and neutron yield are also discussed.",
"title": "Applications of deuterium-tritium equation of state based on density functional theory in inertial confinement fusion",
"URL": "https://aip.scitation.org/doi/full/10.1063/1.4922900",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Work (thermodynamics)",
"Density functional theory",
"Neutron",
"Atomic physics",
"Implosion",
"Computational physics",
"Equation of state",
"Deuterium",
"Compressibility"
],
"year_published": 2015,
"first_author": "Cong Wang",
"scholarly_citations_count": "NaN",
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"sentence": "The results indicate that the peak density predicted by the new equation of state is 10 higher than the quotidian equation of state data.",
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"sentence": "During the implosion, the areal density and neutron yield are also discussed.",
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"entity": "areal density"
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"entity": "implosion"
}
]
}
]
},
{
"abstract": "Planar samples of varying thicknesses of both CH and CD glow discharge polymer have been measured with Fourier transform infrared FTIR spectroscopy before and after exposure to deuterium-tritium DT gas at elevated temperature and pressure. Planar samples of polyimide films made from both hydrogenated and deuterated precursors have also been examined by FTIR before and after DT exposure. The post-exposure FTIR spectra demonstrated no measurable exchange of hydrogen with deuterium or tritium for either polymer. Evidence for oxidation of the glow discharge polymer due to atmospheric oxygen was the only chemical change indicated by the FTIR data.",
"title": "Fourier Transform Infrared Spectroscopic Analysis Of Plastic Capsule Materials Exposed To Deuterium-Tritium (DT) Gas",
"URL": "https://digital.library.unt.edu/ark:/67531/metadc885178/m2/1/high_res_d/888623.pdf",
"fields_of_study": [
"Analytical chemistry",
"Infrared spectroscopy",
"Infrared",
"Fourier transform infrared spectroscopy",
"Materials science",
"Glow discharge",
"Spectroscopy",
"Nuclear magnetic resonance",
"Hydrogen",
"Polymer",
"Deuterium"
],
"year_published": 2006,
"first_author": "Jon R. Schoonover",
"scholarly_citations_count": 1,
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"sentence": "Planar samples of polyimide films made from both hydrogenated and deuterated precursors have also been examined by FTIR before and after DT exposure.",
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},
{
"abstract": "The original description of alpha particle driven instabilities in the Tokamak Fusion Test Reactor in terms of toroidal Alfven eigenmodes TAEs remained inconsistent with three fundamental characteristics of the observations the variation of the mode frequency with toroidal mode number, ii the chirping of the mode frequency for a given toroidal mode number, and iii the antiballooning density perturbation of the modes. It is now shown that these characteristics can be explained by observing that cylindrical-like modes can exist in the weak magnetic shear region of the plasma that then make a transition to TAEs as the central safety factor decreases in time.",
"title": "New interpretation of alpha-particle-driven instabilities in deuterium-tritium experiments on the Tokamak Fusion Test Reactor.",
"URL": "https://link.aps.org/doi/10.1103/PhysRevLett.91.125003",
"fields_of_study": [
"Tokamak",
"Physics",
"Toroid",
"Magnetic confinement fusion",
"Nuclear physics",
"Tokamak Fusion Test Reactor",
"Safety factor",
"Plasma stability",
"Alpha particle",
"Plasma"
],
"year_published": 2003,
"first_author": "Raffi Nazikian",
"scholarly_citations_count": 85,
"NER-RE": [
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"entities": [
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"category": "Plasma property",
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]
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{
"abstract": "The Ben-Gurion University measurements of neutron energy spectra in a graphite stack, resulting from the scattering of 14.7-MeV neutrons streaming through a 6-cm-diam collimator in a 121-cm-thick paraffin wall, have been used as a benchmark for the compatability and accuracy of discrete ordinates, Psub , and transport calculations and as a tool for fusion reactor neutronics. The transport analysis has been carried out with the DOT 4.2 discrete ordinates code and with cross sections processed with the NJOY code. Most of the parameters affecting the accuracy of the flux and L system scattering cross sections in the Psub approximation, the quadrature set employed, and the energy multigroup structure. First, a spectrum calculated with DOT 4.2, with a detector located on the axis of the system, was compared with a spectrum calculated with the MCNP Monte Carlo code, which was a preliminary verification of the DOT 4.2 results. Both calculated spectra were in good agreement. Next, the DOT 4.2 calculations were compared with the measured spectra. The comparison showed that the discrepancies between the measurements and the calculations increase as the distance between the detector and the system axis increases. This trend indicates that when the flux is determined mainlymore by multiple scatterings, a more divided multigroup structure should be employed. less",
"title": "Transport analysis of measured neutron energy spectra in a graphite stack with a collimated deuterium-tritium neutron beam",
"URL": "https://www.tandfonline.com/doi/full/10.13182/NSE89-A23607",
"fields_of_study": [
"Physics",
"Inelastic scattering",
"Neutron",
"Particle detector",
"Atomic physics",
"Elastic scattering",
"Neutron temperature",
"Neutron radiation",
"Collimated light",
"Neutron transport"
],
"year_published": 1989,
"first_author": "R. Ofek",
"scholarly_citations_count": 7,
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"abstract": "A nonuniform layer of deuteriumtritium DT ice inside a spherical inertial confinement fusion ICF target held in an isothermal cryogenic environment should be driven toward uniformity by the betadecay heat of the tritium. Experiments have been performed at KMS fusion to verify this hypothesis. Two major conclusions may be drawn from the initial results 1 the beta decay of the tritium does deposit energy in the target, as evidenced by melting of DT ice when the target is well insulated from its surroundings, and 2 solid layers of DT ice sublime because of betadecay heat. Both conclusions are reinforced by companion studies with nonradioactive hydrogendeuterium HD ice in similar targets held under similar experimental conditions.",
"title": "Experimental verification of beta-decay-driven sublimation in deuterium-tritium ice held in spherical fusion targets",
"URL": "https://www.osti.gov/scitech/biblio/5398723-experimental-verification-beta-decay-driven-sublimation-deuterium-tritium-ice-held-spherical-fusion-targets",
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"Nuclear physics",
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"abstract": "Reaching ignition in direct-drive DD inertial confinement fusion implosions requires achieving central pressures in excess of 100 Gbar. The OMEGA laser system is used to study the physics of implosions that are hydrodynamically equivalent to the ignition designs on the National Ignition Facility NIF. It is shown that the highest hot-spot pressures up to 40 Gbar are achieved in target designs with a fuel adiabat of α 4, an implosion velocity of 3.8 107 cms, and a laser intensity of 1015 Wcm2. These moderate-adiabat implosions are well understood using two-dimensional hydrocode simulations. The performance of lower-adiabat implosions is significantly degraded relative to code predictions, a common feature between DD implosions on OMEGA and indirect-drive cryogenic implosions on the NIF. Simplified theoretical models are developed to gain physical understanding of the implosion dynamics that dictate the target performance. These models indicate that degradations in the shell density and integrity caused by hydrodynamic instabilities during the target acceleration coupled with hydrodynamics at stagnation are the main failure mechanisms in low-adiabat designs. To demonstrate ignition hydrodynamic equivalence in cryogenic implosions on OMEGA, the target-design robustness to hydrodynamic instability growth must be improved by reducing laser-coupling losses caused by cross beam energy transfer.",
"title": "Improving the hot-spot pressure and demonstrating ignition hydrodynamic equivalence in cryogenic deuterium–tritium implosions on OMEGAa)",
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"National Ignition Facility",
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"first_author": "V. N. Goncharov",
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"abstract": "The laser heating of deuterium and tritium ions by small angle DT collisions is calculated assuming that ion distribution functions are displaced Maxwellians with average velocity determined by the laser electric field. For all conditions of high radiation intensity the ion temperature will increase as t25 to good approximation. The heating times are of the order of t109E01010 esu2n1021 cm31λ104 cm2 T108 K52 sec. At high laser fluxes this mechanism dominates electronion heat transfer by several orders of magnitude and results in substantial heating of ions in adjacent nonlaser irradiated plasma, through ionion heat conduction. The heating rate is examined for a plasma of two arbitrary ion species. The heating rate is sensitive to ion masses and charges, and it appears that the above heating time can be shortened by as many as three to five orders of magnitude. A DT plasma may be brought to thermonuclear temperatures by this mechanism, but this requires laser fluxes and laser ene...",
"title": "Deuterium‐Tritium Heating to Thermonuclear Temperatures by Means of Ion‐Ion Collisions in the Presence of Intense Laser Radiation",
"URL": "https://ui.adsabs.harvard.edu/abs/1972PhFl...15.1620M/abstract",
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"Orders of magnitude (temperature)",
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"Thermal conduction",
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"Laser",
"Deuterium",
"Thermonuclear fusion",
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"first_author": "R. C. Mjolsness",
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"abstract": "A discrete spectrum of compressional Alfven eigenmodes and ion-ion hybrid eigenmodes is found to exist above the tritium ion cyclotron frequency in the deuterium-tritium D-T plasma of a spherical tokamak power plant STPP. An equilibrium magnetic well formed in a STPP, as a result of plasma diamagnetism, causes all externally launched electromagnetic waves to propagate from the side of high total magnetic field, and it is this well that forms discrete spectra in the ion cyclotron resonance heating frequency range near the plasma core. The eigenmodes, as well as the position of the mode conversion layers, are obtained in a one-dimensional magnetic field geometry, relevant for the STPP, which will necessarily operate at high β. The possibility of using the discrete spectrum probed with an external antenna, or driven by energetic ions, for measuring the D-T...",
"title": "Compressional Alfvén and ion-ion hybrid modes in the deuterium-tritium plasma of a spherical tokamak power plant",
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"abstract": "The first measurements of multiple, high-pressure shock waves in cryogenic deuterium-tritium DT ice layered capsule implosions on the National Ignition Facility have been performed. The strength and relative timing of these shocks must be adjusted to very high precision in order to keep the DT fuel entropy low and compressibility high. All previous measurements of shock timing in inertial confinement fusion implosions have been performed in surrogate targets, where the solid DT ice shell and central DT gas regions were replaced with a continuous liquid deuterium D2 fill. This report presents the first experimental validation of the assumptions underlying this surrogate technique.",
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{
"abstract": "Summary form only given, as follows. In the course of the preliminary tritium experiment PTE in JET, where combined D and T neutral beam injection generated a DT fusion power of 1.7 MW, ion cyclotron emission ICE in the frequency range up to 180 MHz was measured using an ICRF heating antenna as probe. The ICE spectrum showed a number of superthermal narrow, equally spaced emission lines which correspond to deuteron or alpha-particle ion cyclotron harmonics at the outer mid-plane edge major radius R approximately 4 . DD and DT power spectra are similar in form, and show split lines which, above approximately 100 MHz, merge into a continuum. With tritium injection, the ICE power increased by a factor comparable to the increase of neutron flux, indicating that 3.5 MeV fusion alpha-particles provide the free energy for generating ICE. The ICE power increases almost linearly with neutron flux over a range of six decades. The evolution of the ICE follows the rise of the neutron flux, but is delayed by a time comparable with the slowing-down time of the alpha-particles. The ICE intensity is anti-correlated with large amplitude edge-localized modes.",
"title": "Identification of ion cyclotron emission from fusion alpha particles during jet deuterium-tritium experiments",
"URL": "NaN",
"fields_of_study": [
"Cyclotron",
"Physics",
"Alpha particle",
"Atomic physics",
"Nuclear physics",
"Neutron",
"Neutral beam injection",
"Deuterium",
"Ion",
"Plasma",
"Tokamak",
"Quantum mechanics"
],
"year_published": 1992,
"first_author": "G Cottrell",
"scholarly_citations_count": "NaN",
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{
"abstract": "During its tritium campaign the Tokamak Fusion Test Reactor produced more than 750 deuteriumtritium DT shots involving at least one tritium neutral beam, and some 20 000 shots with D beams and no T beams. A calibrated system of four fission chambers and two Si surface barrier threshold detectors SBDs monitored the fusion neutron production rate in all these shots, while elemental activation foils measured total yields, Y, on more than 300 DT shots. The baseline fission-detector current and log-Campbell modes had stable detection efficiencies throughout the DT campaign, but there were several cross-calibration corrections as large as 10 to the efficiencies of the count-rate and log-Campbell modes of some backup fission chambers and of the collimated SBD detector. For Y31016 neutrons per shot, the ratio of fission-chamber and SBD yields to activation yields varied between 0.88 and 1.1, with an average value of 0.960.99 that was fairly constant throughout the DT period. All detectors and electro...",
"title": "Long-term performance of neutron detectors during deuterium–tritium operation in the Tokamak Fusion Test Reactor",
"URL": "http://www.osti.gov/scitech/biblio/295682-long-term-performance-neutron-detectors-during-deuterium-endash-tritium-operation-tokamak-fusion-test-reactor",
"fields_of_study": [
"Physics",
"Fission",
"Neutron",
"Nuclear physics",
"Tokamak Fusion Test Reactor",
"Collimated light",
"Plasma diagnostics",
"Deuterium",
"Tritium",
"Neutron detection"
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"year_published": 1999,
"first_author": "D. L. Jassby",
"scholarly_citations_count": 1,
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"abstract": "In this paper,for designing a neutron source,the neutron yield of Td,n4He reaction at 120 keV of incident deuteron energy is calculated by a mathematical method.The neutron yield by the incident beams of different percentages of Dand D2was studied.The neutron yield increase effectively with the percentage of Dand decreases with increasing percentages of D2.The effects of different target materials and components on the neutron yield are studied.The neutron yield is in proportion to the content of the tritium and in inverse proportion to the target atomic mass.Parameters of the ion source and the thick target are analyzed for improving performance of the neutron source.Effects of the oxide layer or film coatings in surface of the titanium tritide film on neutron yield are calculated,too.The results are compared with experimental results.A novel target design is introduced and its feasibility is studied.",
"title": "Effects of ion source and target thickness on neutron yield from deuterium-tritium reaction neutron source",
"URL": "https://inis.iaea.org/Search/search.aspx?orig_q=RN:47057237",
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"Analytical chemistry",
"Neutron",
"Radiochemistry",
"Neutron source",
"Neutron generator",
"Materials science",
"Neutron temperature",
"Neutron capture",
"Neutron cross section",
"Neutron probe",
"Neutron stimulated emission computed tomography"
],
"year_published": 2012,
"first_author": "Yang Zhen",
"scholarly_citations_count": 3,
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"sentence": "Effects of the oxide layer or film coatings in surface of the titanium tritide film on neutron yield are calculated,too.",
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{
"abstract": "The resolution and analysis of the components in hydrogen-- deuterium-- tritium mixtures were accomplished by gas chromatography at 77 deg K. Tritium was incorporated into the sample mixtures in tracer quantities Nsub Tsub 2 10 sup-4, 2 10sup-1 mC per standard ml. Helium, hydrogen, and neon were employed as carrier gases with several columns containing activated alumina and ferric oxide on alumina. Varying degrees of isotope separation were observed with different carriers, adsorbents, and conditions of column activation. Separation factors for the hydrogen isotopes and isomers on various columns at 77 deg K were calculated. Flow-modified ionization chambers and a Cary Model 31 vibrating reed electrometer equipped with a 10sup 10 or 10sup 11 ohm leak resistor were employed in series with thermistor-equipped katharometers for the detection of radioactive and non-radioactive hydrogen isotopes. Oatputs from the electrometer and the katharometer were recorded simultaneously on two synchronized Brown electronic recorders. Simultaneous ionization chamber and katharometer detection of para-hydrogen, ortho-hydrogen, hydrogen deuteride, and deuterium was observed. auth",
"title": "THE SEPARATION OF HYDROGEN, HYDROGEN DEUTERIDE, TRITIUM HYDRIDE, DEUTERIUM, TRITIUM DEUTERIDE, AND TRITIUM MIXTURES BY GAS CHROMATOGRAPHY",
"URL": "http://www.osti.gov/scitech/biblio/4659803-separation-hydrogen-hydrogen-deuteride-tritium-hydride-deuterium-tritium-deuteride-tritium-mixtures-gas-chromatography",
"fields_of_study": [
"Analytical chemistry",
"Radiochemistry",
"Chemistry",
"Isotope separation",
"Hydrogen deuteride",
"Hydride",
"Hydrogen",
"Neon",
"Helium",
"Deuterium",
"Tritium"
],
"year_published": 1963,
"first_author": "Edward H. Carter",
"scholarly_citations_count": 41,
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"sentence": "Separation factors for the hydrogen isotopes and isomers on various columns at 77 deg K were calculated.",
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"sentence": "Simultaneous ionization chamber and katharometer detection of para-hydrogen, ortho-hydrogen, hydrogen deuteride, and deuterium was observed.",
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{
"abstract": "The experiments performed in the Japan Atomic Energy Research InstituteU.S. Department of Energy collaborative program on fusion blanket neutronics are designed with consideration of geometrical and material configurations. The general guide that is used to design the engineering-oriented neutronics experiment, which uses an accelerator-based 14-MeV neutron source, is discussed and compared with neutronics characteristics of the reactor models. Preparation of the experimental assembly, blanket materials, and the neutron source is described. A variety of techniques for measuring the nuclear parameters such as the tritium production rate are developed or introduced through the collaboration as a basis of the neutronics experiments. The features of these techniques are discussed with the experimental error and compared with each other. 25 refs., 15 figs., 4 tabs.",
"title": "Design and Techniques for Fusion Blanket Neutronics Experiments Using an Accelerator-Based Deuterium-Tritium Neutron Source",
"URL": "https://www.ans.org/pubs/journals/fst/a_30401",
"fields_of_study": [
"Nuclear engineering",
"Fusion",
"Neutron source",
"Nuclear physics",
"Particle accelerator",
"Materials science",
"Blanket",
"Scintillation counter",
"Deuterium",
"Tritium",
"Neutron transport"
],
"year_published": 1995,
"first_author": "Yukio Oyama",
"scholarly_citations_count": 4,
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{
"abstract": "Abstract Removal of helium ash and the anomalous transport of deuterium D and tritium T ions driven by collisionless trapped electron mode CTEM turbulence in tokamak plasmas with weak magnetic shear are studied. We derive the eigenvalue of CTEM with helium ash, and calculate the quasi-linear turbulent fluxes of helium ash, D and T ions simultaneously. Based on the analytical results, the parametric dependence of CTEM instability as well as the anomalous transport of helium ash and D-T ions is investigated, in order to explore the parameter region that is favorable for expelling more helium ash than D and T ions. It is found that helium ash with higher temperature and steeper density profile plays a role of destabilizing CTEM instability, and has higher transport level than that of T ions. We also find that increasing electron temperature and flattening electron density profile are favorable for exhausting helium ash. Isotopic effects .. increasing the fraction of T ions enhance the transport of both helium ash and D-T ions. Moreover, the trend of stronger transport level of helium ash than that of D-T ions is enhanced by raising electron temperature and flattening electron density profile as well as isotopic effects. Besides, the diffusivity is much larger than the convection. This indicates that the CTEM turbulence driven helium ash transport is favorable for removing helium ash under the parameter region used in the present paper. The possible relevance of our theoretical results to experimental observations is also discussed.",
"title": "The role of collisionless trapped electron mode turbulence on removal of helium ash and transport of deuterium-tritium ions",
"URL": "https://www.scilit.net/article/429ba25f51881513272d2cade2c050d9",
"fields_of_study": [
"Mode (statistics)",
"Ion",
"Electron",
"Atomic physics",
"Materials science",
"Turbulence",
"Helium",
"Deuterium",
"Tritium"
],
"year_published": 2020,
"first_author": "Weixin Guo",
"scholarly_citations_count": 8,
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"title": "A polar direct drive liquid deuterium-tritium wetted foam target concept for inertial confinement fusion",
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"abstract": "Accurate knowledge of the equation of state EOS of deuteriumtritium DT mixtures is critically important for inertial confinement fusion ICF. Although the study of EOS is an old topic, there is a longstanding lack of global accurate EOS data for DT within a unified theoretical framework. DT fuel goes through very wide ranges of density and temperature from a cold condensed state to a hot dense plasma where ions are in a moderately or even strongly coupled state and electrons are in a partially or strongly degenerate state. The biggest challenge faced when using first-principles methods for obtaining accurate EOS data for DT fuel is the treatment of electronion interactions and the extremely high computational cost at high temperatures. In the present work, we perform extensive state-of-the-art ab initio quantum Langevin molecular dynamics simulations to obtain EOS data for DT mixtures at densities from 0.1 gcm3 to 2000 gcm3 and temperatures from 500 K to 2000 eV, which are relevant to ICF processes. Comparisons with average-atom molecular dynamics and orbital-free molecular dynamics simulations show that the ionic strong-coupling effect is important for determining the whole-range EOS. This work can supply accurate EOS data for DT mixtures within a unified ab initio framework, as well as providing a benchmark for various semiclassical methods.",
"title": "Unified first-principles equations of state of deuterium-tritium mixtures in the global inertial confinement fusion region",
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"title": "A polar direct drive liquid deuterium–tritium wetted foam target concept for inertial confinement fusion",
"URL": "https://aip.scitation.org/doi/10.1063/5.0062590",
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"abstract": "Solid-state fuel ignition was given by Chu and Bobin according to the hydrodynamic theory at 0 qualitatively. A high threshold energy flux density, .., E 4.3 1012 Jm2, has been reached. Recently, fast ignition by employing clean petawattpicosecond laser pulses was performed. The anomalous phenomena were observed to be based on suppression of prepulses. The accelerated plasma block was used to ignite deuteriumtritium fuel at solid-state density. The detailed analysis of the thermonuclear wave propagation was investigated. Also the fusion conditions at 0 layers were clarified by exactly solving hydrodynamic equations for plasma block ignition. In this paper, the applied physical mechanisms are determined for nonlinear force laser driven plasma blocks, thermonuclear reaction, heat transfer, electronion equilibration, stopping power of alpha particles, bremsstrahlung, expansion, density dependence, and fluid dynamics. New ignition conditions may be obtained by using temperature equations, including the density profile that is obtained by the continuity equation and expansion velocity. The density is only a function of and independent of time. The ignition energy flux density, Et, for the 0 layers is 1.95 1012 Jm2. Thus threshold ignition energy in comparison with that at 0 layers would be reduced to less than 50 percent.",
"title": "In depth fusion flame spreading with a deuterium—tritium plane fuel density profile for plasma block ignition",
"URL": "http://ui.adsabs.harvard.edu/abs/2012ChPhB..21l5201M/abstract",
"fields_of_study": [
"Minimum ignition energy",
"Stopping power (particle radiation)",
"Ignition system",
"Continuity equation",
"Atomic physics",
"Materials science",
"Threshold energy",
"Energy flux",
"Thermonuclear fusion",
"Plasma"
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"year_published": 2012,
"first_author": "B. Malekynia",
"scholarly_citations_count": 5,
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"abstract": "Utilizing the energy released from the nuclear fusion of deuterium with tritium D-T may be an important method of supplying energy in the future. The ionizing radiation emitted from nuclear fusion is a potential health risk to humans, including scientists who are currently performing nuclear fusion experiments and the employees of fusion nuclear plants, in the future. However, there have been few reports on the biological effects of fusion radiation. In the present study, using the High Intensity D-T Fusion Neutron Generator, the DNA damage and its regulation in normal human fibroblasts exposed to fusion radiation were investigated. Heme oxygenase 1 HO-1, which is reported to induce anti-inflammatory activity, was upregulated in the irradiated cells. Pretreatment with the HO-1 inhibitor, protoporphyrin IX zinc II, exacerbated double strand break formation following exposure to fusion radiation. The expression of cyclooxygenase-2 COX-2 contributed to the upregulation of HO-1, as demonstrated by the result that its inhibitor, NS-398, inhibited the induction of HO-1 in irradiated cells. It was further clarified that the ataxia telangiectasia mutated DNA damage response was activated and it stimulated the phosphorylation of p38 mitogen-activated protein kinase, which was responsible for the upregulation of COX-2 and HO-1. These results provide novel information on fusion radiation-induced biological effects and potential targets for decreasing the associated health risks.",
"title": "Cyclooxygenase‑2‑mediated upregulation of heme oxygenase 1 mitigates the toxicity of deuterium‑tritium fusion radiation",
"URL": "https://www.spandidos-publications.com/10.3892/ijmm.2018.3799",
"fields_of_study": [
"Downregulation and upregulation",
"DNA damage",
"Ionizing radiation",
"Chemistry",
"Heme oxygenase",
"Protoporphyrin IX",
"Cell cycle",
"Tritium",
"Nuclear fusion",
"Cell biology"
],
"year_published": 2018,
"first_author": "Xiaoyao Yang",
"scholarly_citations_count": 3,
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"abstract": "It has recently been shown that when solid tritium is confined in an isothermal enclosure, self-heating due to beta decay drives a net sublimation of material from thick, warmer layers to thin, cooler ones, ultimately resulting in layer thickness uniformity. We have observed this process of beta-layering in a 50-50 D-T mixture in both cylindrical and spherical enclosures at temperatures from 19.6 K, down to 11.6 K. The measured time constants are found to depend on the 3He content as suggested by recent theoretical predictions. When using an enclosure having low thermal conductivity, the ultimate layer uniformity is found to be a strong function of the exchange gas pressure. This is due to the presence of thermal convection in the exchange gas and consequent temperature anisotropy at the solid layer surface.",
"title": "The effects of exchange gas temperature and pressure on the beta-layering process in solid deuterium-tritium fusion fuel",
"URL": "https://digital.library.unt.edu/ark:/67531/metadc1189075/m2/1/high_res_d/6934901.pdf",
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"Tritium",
"Layering",
"Sublimation (psychology)",
"Thermal conductivity",
"Materials science",
"Deuterium",
"Isothermal process",
"Thermodynamics",
"Chemistry",
"Analytical Chemistry (journal)",
"Composite material",
"Nuclear physics",
"Chromatography",
"Psychology",
"Botany",
"Physics",
"Psychotherapist",
"Biology"
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"year_published": 1990,
"first_author": "J Hoffer",
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{
"abstract": "Summary form only given, as follows. In the course of the preliminary tritium experiment PTE in JET, where combined D and T neutral beam injection generated a DT fusion power of 1.7 MW, ion cyclotron emission ICE in the frequency range up to 180 MHz was measured using an ICRF heating antenna as probe. The ICE spectrum showed a number of superthermal narrow, equally spaced emission lines which correspond to deuteron or alpha-particle ion cyclotron harmonics at the outer mid-plane edge major radius R approximately 4 . DD and DT power spectra are similar in form, and show split lines which, above approximately 100 MHz, merge into a continuum. With tritium injection, the ICE power increased by a factor comparable to the increase of neutron flux, indicating that 3.5 MeV fusion alpha-particles provide the free energy for generating ICE. The ICE power increases almost linearly with neutron flux over a range of six decades. The evolution of the ICE follows the rise of the neutron flux, but is delayed by a time comparable with the slowing-down time of the alpha-particles. The ICE intensity is anti-correlated with large amplitude edge-localized modes.",
"title": "Identification of ion cyclotron emission from fusion alpha particles during JET deuterium-tritium experiments",
"URL": "http://ui.adsabs.harvard.edu/abs/1992PPCF...34.1969C/abstract",
"fields_of_study": [
"Ion",
"Atomic physics",
"Nuclear physics",
"Materials science",
"Fusion power",
"Neutral beam injection",
"Cyclotron",
"Deuterium",
"Alpha particle",
"Neutron flux",
"Emission spectrum"
],
"year_published": 1992,
"first_author": "G.A. Cottrell",
"scholarly_citations_count": "NaN",
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"abstract": "Neutronics experiment for two types of heterogeneous blankets are performed in the Phase-IIC experiments of the Japan Atomic Energy Research InstituteU.S. Department of Energy collaborative program on fusion blanket neutronics. The experimental system uses the same geometry as the previous Phase-IIA series, which was a closed geometry that used a neutron source enclosure of lithium carbonate. The heterogeneities selected for testing are the beryllium edge-on and the water coolant channel assemblies that appear in typical blankets. In the former, the beryllium and the lithium-oxide LiO layers are piled up alternately in the front part of the test blanket. In the latter, the two simulated water cooling channels are emplaced vertically in the LiO blanket. These channels produce a steep gradient of neutron flux and a significant spectrum change around the material boundary. The calculation accuracy and measurement method for these transient regions are key areas of interest in the experiments. The measurements are performed for the tritium production rate and the other nuclear parameters as well as the previous experiments. The void effect is found to not be negligible around the heterogeneous region for the detector with a low-energy response. At the same time, enhancements of tritium productionmore are seen near the beryllium and hydrogenous material. However, the current Monte Carlo calculation shows good agreement with the experiment even in such a boundary. 22 refs., 20 figs., 7 tabs. less",
"title": "Neutronics Integral Experiments of Lithium-Oxide Fusion Blanket with Heterogeneous Configurations Using Deuterium-Tritium Neutrons",
"URL": "http://www.osti.gov/scitech/biblio/121590-neutronics-integral-experiments-lithium-oxide-fusion-blanket-heterogeneous-configurations-using-deuterium-tritium-neutrons",
"fields_of_study": [
"Nuclear engineering",
"Neutron",
"Neutron source",
"Nuclear physics",
"Monte Carlo method",
"Blanket",
"Beryllium",
"Deuterium",
"Neutron transport",
"Neutron flux"
],
"year_published": 1995,
"first_author": "Yukio Oyama",
"scholarly_citations_count": 5,
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"abstract": "Volume ignition is an alternative approach to inertial confinement fusion. Due to igniting the whole fuel region rather than the central hot spot compared with the central hot-spot ignition, more laser energy is needed for volume ignition. Therefore, it is much desirable to examine the ignition margin for volume ignition. Hydrodynamic instabilities are major factors responsible for degrading inertial confinement fusion implosion performance. Hydrodynamic instabilities usually bring dramatic deformations of the fuel target, and accordingly, more radiation energy loss leaks from the fuel region. Therefore, the focus of this paper is on how they influence the radiation energy loss and increase critical temperatures for volume ignition. The present results show that critical ignition temperature increases both with the perturbation mode number and the perturbation amplitudes. What is more, we find that perturbations with longitudinal mode have a greater impact than those with latitudinal mode, and targets with lower deuteriumtritium mass are more vulnerable to perturbations. The present results are important and offer support for subsequent ignition-target design.",
"title": "Critical temperature for volume ignition of deuterium–tritium fuel in inertial confinement fusion: Effects of hydrodynamic instabilities",
"URL": "NaN",
"fields_of_study": [
"Ignition system",
"Implosion",
"Physics",
"Inertial confinement fusion",
"Mechanics",
"National Ignition Facility",
"Volume (thermodynamics)",
"Nuclear engineering",
"Fusion power",
"Nuclear physics",
"Plasma",
"Thermodynamics",
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"year_published": 2022,
"first_author": "Rui-Hua Xu",
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"sentence": "What is more, we find that perturbations with longitudinal mode have a greater impact than those with latitudinal mode, and targets with lower deuteriumtritium mass are more vulnerable to perturbations.",
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"category": "Nuclear Fusion System Component",
"entity": "target"
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"abstract": "A correlation between the measured alpha particle loss and high frequency kHz magnetohydrodynamic MHD modes has been observed in some high ensuremath plasma pressuremagnetic pressure DT plasmas in TFTR. These modes are localized around the peak plasma pressure gradient and have ballooning characteristics. Particle simulation shows that the loss is due to wave-particle resonances. Linear instability analysis indicates that the plasma is unstable to the kinetic MHD ballooning modes driven by strong local pressure gradients.",
"title": "First observation of alpha particle loss induced by kinetic ballooning modes in TFTR deuterium-tritium experiments.",
"URL": "https://www.ncbi.nlm.nih.gov/pubmed/10061626",
"fields_of_study": [
"Physics",
"Atomic physics",
"Instability",
"Beta (plasma physics)",
"Magnetohydrodynamics",
"Magnetic pressure",
"Alpha particle",
"Plasma",
"Atmospheric-pressure plasma",
"Pressure gradient"
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"year_published": 1996,
"first_author": "Z. Chang",
"scholarly_citations_count": 26,
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"sentence": "Linear instability analysis indicates that the plasma is unstable to the kinetic MHD ballooning modes driven by strong local pressure gradients.",
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"abstract": "The 350-keV Cockroft-Walton accelerator at Sandia National laboratorys Ion Beam facility is being used to calibrate absolutely a total DT neutron yield diagnostic based on the 63Cun,2n62Cuβ reaction. These investigations have led to first-order uncertainties approaching 5 or better. The experiments employ the associated-particle technique. Deuterons at 175 keV impinge a 2.6 μm thick erbium tritide target producing 14.1 MeV neutrons from the Td,n4He reaction. The alpha particles emitted are measured at two angles relative to the beam direction and used to infer the neutron flux on a copper sample. The induced 62Cu activity is then measured and related to the neutron flux. This method is known as the F-factor technique. Description of the associated-particle method, copper sample geometries employed, and the present estimates of the uncertainties to the F-factor obtained are given.",
"title": "Progress in obtaining an absolute calibration of a total deuterium-tritium neutron yield diagnostic based on copper activation.",
"URL": "http://www.osti.gov/scitech/biblio/22093880",
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"Neutron scattering",
"Physics",
"Neutron",
"Nuclear physics",
"Neutron activation analysis",
"Ion beam",
"Neutron cross section",
"Deuterium",
"Radiation flux",
"Neutron flux"
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"year_published": 2012,
"first_author": "Carlos L. Ruiz",
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"abstract": "Rate coefficients and normalized differential scattering rate distributions for -, -, -, and -sup 6Li elastic reactions for radially translating Maxwellian-distributed targets are examined for energy and temperature ranges related to fusion energies. For these reactions, both asymptotically constant cross sections and cross sections decaying inversely as the relative speed are treated. For the -, ,, and -sup 6Li cases, actual multigroup cross sections are employed in the energy range from 0 to 17 MeV, while the - interaction is treated in the hard sphere limit. Some results for various incident and final neutron energies at a target temperature of 2 MeV are listed, and conclusions from an extensive numerical analysis are given.",
"title": "Elastic Neutron Scattering from Distributed Fusion Neutrons, Deuterium, Tritium, and Lithium, and Multigroup Rate Coefficients",
"URL": "https://www.ans.org/pubs/journals/nse/a_27036",
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"Neutron scattering",
"Physics",
"Neutron",
"Atomic physics",
"Nuclear physics",
"Scattering",
"Elastic scattering",
"Nuclear reaction",
"Scattering rate",
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"Deuterium"
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"year_published": 1977,
"first_author": "B. R. Wienke",
"scholarly_citations_count": 1,
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"abstract": "It has recently been shown that when solid tritium is confined in an isothermal enclosure, self-heating due to beta decay drives a net sublimation of material from thick, warmer layers to thin, cooler ones, ultimately resulting in layer thickness uniformity. We have observed this process of beta-layering in a 50--50 D-T mixture in both cylindrical and spherical enclosures at temperatures from 19.6 K, down to 11.6 K. The measured time constants are found to depend on the He content as suggested by recent theoretical predictions. When using an enclosure having low thermal conductivity, the ultimate layer uniformity is found to be a strong function of the exchange gas pressure. This is due to the presence of thermal convection in the exchange gas and consequent temperature anisotropy at the solid layer surface. 6 refs., 2 figs., 1 tab.",
"title": "The effects of exchange gas temperature and pressure on the beta-layering process in solid deuterium-tritium fusion fuel",
"URL": "https://www.sciencedirect.com/science/article/pii/S0921452690809318",
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"Nuclear physics",
"Materials science",
"Radioactive decay",
"Convective heat transfer",
"Sublimation (phase transition)",
"Deuterium",
"Anisotropy",
"Thermal conductivity",
"Thermodynamics",
"Enclosure"
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"abstract": "We discuss the analyses of gated, -ray imaging data from polar-direct-drive experiments with cryogenically layered deuterium-tritium targets on the OMEGA laser. The in-flight shell asymmetries were diagnosed at various times during the implosion, which was caused by the beam pointing geometry and preimposed variations in the energy partition between the different groups of laser beams. The shape of the ablation surface during the acceleration phase of the implosion was measured along two different lines of sight, and a Legendre mode ℓ-mode decomposition was applied for modes of up to ten to investigate shell asymmetries. A clear causal relationship between the imposed beam imbalance and the shape of the in-flight shell asymmetries was observed. The imploded shell with a balanced energy ratio shows smaller values of the amplitudes of ℓ-mode 2 compared to that from implosions with an imbalanced ring energy ratio. The amplitudes of ℓ-modes 4 and 6 are the same within the measurement uncertainty with respect to the change in beam energy ratio.",
"title": "Diagnosis of the imploding shell asymmetry in polar-direct-drive deuterium-tritium cryogenic target implosions on OMEGA.",
"URL": "https://aip.scitation.org/doi/10.1063/5.0101567",
"fields_of_study": [
"Implosion",
"Physics",
"Atomic physics",
"Inertial confinement fusion",
"Shell (structure)",
"Deuterium",
"Amplitude",
"Omega",
"Plasma diagnostics",
"Plasma",
"Nuclear physics",
"Laser",
"Optics",
"Materials science",
"Quantum mechanics",
"Composite material"
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"year_published": 2022,
"first_author": "T R Joshi",
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"category": "Physical Process",
"entity": "Implosion"
},
{
"category": "Plasma property",
"entity": "Shell asymmetries"
},
{
"category": "Detection and Monitoring Systems",
"entity": "Legendre mode decomposition"
},
{
"category": "Plasma dynamic and behavior",
"entity": "Shell asymmetries"
},
{
"category": "Physics Entity",
"entity": "Legendre mode"
},
{
"category": "Physics Entity",
"entity": "ℓ-mode"
}
]
},
{
"sentence": "A clear causal relationship between the imposed beam imbalance and the shape of the in-flight shell asymmetries was observed.",
"entities": [
{
"category": "Nuclear Fusion System Component",
"entity": "shell"
},
{
"category": "Nuclear Fusion System Component",
"entity": "beam"
},
{
"category": "Plasma property",
"entity": "asymmetries"
}
]
},
{
"sentence": "The imploded shell with a balanced energy ratio shows smaller values of the amplitudes of ℓ-mode 2 compared to that from implosions with an imbalanced ring energy ratio.",
"entities": [
{
"category": "Plasma property",
"entity": "amplitudes of ℓ-mode 2"
},
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},
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"category": "Nuclear Fusion System Configuration",
"entity": "implosions with an imbalanced ring energy ratio"
}
]
},
{
"sentence": "The amplitudes of ℓ-modes 4 and 6 are the same within the measurement uncertainty with respect to the change in beam energy ratio.",
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"category": "Plasma property",
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]
}
]
},
{
"abstract": "We report on the first layered deuterium-tritium DT capsule implosions indirectly driven by a high-foot laser pulse that were fielded in depleted uranium hohlraums at the National Ignition Facility. Recently, high-foot implosions have demonstrated improved resistance to ablation-front Rayleigh-Taylor instability induced mixing of ablator material into the DT hot spot. Uranium hohlraums provide a higher albedo and thus an increased drive equivalent to an additional 25 TW laser power at the peak of the drive compared to standard gold hohlraums leading to higher implosion velocity. Additionally, we observe an improved hot-spot shape closer to round which indicates enhanced drive from the waist. In contrast to findings in the National Ignition Campaign, now all of our highest performing experiments have been done in uranium hohlraums and achieved total yields approaching 10 neutrons where more than 50 of the yield was due to additional heating of alpha particles stopping in the DT fuel.",
"title": "Demonstration of High Performance in Layered Deuterium-Tritium Capsule Implosions in Uranium Hohlraums at the National Ignition Facility.",
"URL": "http://europepmc.org/abstract/MED/26274424",
"fields_of_study": [
"Nuclear engineering",
"Nova (laser)",
"Depleted uranium",
"Ignition system",
"Nuclear physics",
"Materials science",
"Implosion",
"Fusion power",
"National Ignition Facility",
"Hohlraum",
"Uranium"
],
"year_published": 2015,
"first_author": "Tilo Döppner",
"scholarly_citations_count": 102,
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"entity": "Laser"
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"sentence": "Additionally, we observe an improved hot-spot shape closer to round which indicates enhanced drive from the waist.",
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"category": "Plasma region",
"entity": "waist"
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"category": "Plasma property",
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]
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"sentence": "In contrast to findings in the National Ignition Campaign, now all of our highest performing experiments have been done in uranium hohlraums and achieved total yields approaching 10 neutrons where more than 50 of the yield was due to additional heating of alpha particles stopping in the DT fuel.",
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{
"category": "Chemical Element or Compound",
"entity": "Uranium"
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"entity": "Hohlraums"
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{
"category": "Particle",
"entity": "Alpha particles"
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"category": "Nuclear Fusion Experimental Facility",
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{
"abstract": "The toroidal Alfven eigenmodes TAE are calculated to be stable in the presently obtained deuteriumtritium plasmas in the Tokamak Fusion Test Reactor TFTR. However, the core localized TAE mode can exist and is less stable than the global TAE modes. The beam ion Landau damping and the radiative damping are the two main stabilizing mechanisms in the present calculation. In future deuteriumtritium experiments, the alphadriven TAE modes are predicted to occur with a weakly reversed shear profile.",
"title": "Analysis of alpha particle‐driven toroidal Alfvén eigenmodes in Tokamak Fusion Test Reactor deuterium–tritium experiments",
"URL": "https://aip.scitation.org/doi/10.1063/1.871537",
"fields_of_study": [
"Physics",
"Toroid",
"Beam (structure)",
"Atomic physics",
"Nuclear physics",
"Tokamak Fusion Test Reactor",
"Deuterium",
"Alpha particle",
"Landau damping",
"Radiative transfer",
"Plasma"
],
"year_published": 1996,
"first_author": "Guoyong Fu",
"scholarly_citations_count": 76,
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"category": "Nuclear Fusion Device Type",
"entity": "Tokamak"
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"entity": "deuterium-tritium plasmas"
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"sentence": "However, the core localized TAE mode can exist and is less stable than the global TAE modes.",
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"sentence": "The beam ion Landau damping and the radiative damping are the two main stabilizing mechanisms in the present calculation.",
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"sentence": "In future deuteriumtritium experiments, the alphadriven TAE modes are predicted to occur with a weakly reversed shear profile.",
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"category": "Particle",
"entity": "alpha"
},
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"category": "Chemical Element or Compound",
"entity": "deuterium"
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{
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"category": "Field Configuration",
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{
"abstract": "A conceptual design of a beam-shaping assembly for boron neutron capture therapy using deuteriumtritium accelerator based neutrons source is developed. Calculations based on a simple geometry model for the radiation transport are initially performed to estimate the assembly materials and their linear dimensions. Afterward, the assembly geometry is produced, optimized and verified. In order to perform these calculations the general-purpose MCNP code is used. Irradiation time and therapeutic gain are utilized as beam assessment parameters. Metallic uranium and manganese are successfully tested for fast-to-epithermal neutron moderation. In the present beam-shaping assembly proposal, the therapeutic gain is improved by 23 and the accelerator current required for a fixed irradiation period is reduced by six times compared to previous proposals based on the same DT reaction.",
"title": "A conceptual design of a beam-shaping assembly for boron neutron capture therapy based on deuterium-tritium neutron generators.",
"URL": "http://onlinelibrary.wiley.com/doi/10.1118/1.1702308/abstract",
"fields_of_study": [
"Nuclear engineering",
"Conceptual design",
"Neutron moderator",
"Neutron",
"Beam (structure)",
"Neutron source",
"Neutron generator",
"Materials science",
"Nuclear medicine",
"Neutron capture",
"Deuterium"
],
"year_published": 2004,
"first_author": "Guido Martı́n",
"scholarly_citations_count": 18,
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"entity": "boron neutron capture therapy"
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"category": "Experimental Apparatus",
"entity": "beam-shaping assembly"
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"category": "Chemical Element or Compound",
"entity": "deuterium"
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{
"category": "Chemical Element or Compound",
"entity": "tritium"
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{
"category": "Chemical Element or Compound",
"entity": "boron"
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]
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"sentence": "Calculations based on a simple geometry model for the radiation transport are initially performed to estimate the assembly materials and their linear dimensions.",
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]
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{
"sentence": "Afterward, the assembly geometry is produced, optimized and verified.",
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"category": "Nuclear Fusion System Component",
"entity": "assembly geometry"
}
]
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{
"sentence": "In order to perform these calculations the general-purpose MCNP code is used.",
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{
"category": "Software and simulation",
"entity": "MCNP code"
}
]
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"sentence": "Irradiation time and therapeutic gain are utilized as beam assessment parameters.",
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"sentence": "Metallic uranium and manganese are successfully tested for fast-to-epithermal neutron moderation.",
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"entity": "Uranium"
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"category": "Chemical Element or Compound",
"entity": "Manganese"
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{
"category": "Particle",
"entity": "Neutron"
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"category": "Physical Process",
"entity": "Neutron moderation"
}
]
},
{
"sentence": "In the present beam-shaping assembly proposal, the therapeutic gain is improved by 23 and the accelerator current required for a fixed irradiation period is reduced by six times compared to previous proposals based on the same DT reaction.",
"entities": [
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"category": "Nuclear Fusion Technique",
"entity": "DT reaction"
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"category": "Nuclear Fusion System Component",
"entity": "beam-shaping assembly"
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"category": "Experimental Apparatus",
"entity": "accelerator"
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]
}
]
},
{
"abstract": "The dispersion and damping rate of the ion acoustic waves IAWs in deuteriumtritium DT fusion plasmas with slowing-down distributed α particles are investigated within the framework of kinetic theory. It is shown that the concentration of α particles has an important effect on IAWs. The frequency of IAWs decreases as the α concentration increases. Inversely, the damping rate increases as the α concentration increases. The results for slowing-down distributed α particles are compared with those obtained when α particles are assumed to have an equivalent Maxwellian distribution.",
"title": "Dispersion and damping of ion acoustic wave in deuterium–tritium fusion plasmas with slowing-down distributed α particles",
"URL": "https://aip.scitation.org/doi/10.1063/5.0045555",
"fields_of_study": [
"Ion acoustic wave",
"Ion",
"Atomic physics",
"Materials science",
"Acoustic wave",
"Kinetic theory of gases",
"α particles",
"Deuterium",
"Tritium",
"Dispersion (chemistry)"
],
"year_published": 2021,
"first_author": "F. F. Lu",
"scholarly_citations_count": 2,
"NER-RE": [
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"sentence": "The dispersion and damping rate of the ion acoustic waves IAWs in deuteriumtritium DT fusion plasmas with slowing-down distributed α particles are investigated within the framework of kinetic theory.",
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"category": "Particle",
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"sentence": "It is shown that the concentration of α particles has an important effect on IAWs.",
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"entity": "IAWs"
}
]
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{
"sentence": "The frequency of IAWs decreases as the α concentration increases.",
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"entity": "α"
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{
"sentence": "The results for slowing-down distributed α particles are compared with those obtained when α particles are assumed to have an equivalent Maxwellian distribution.",
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"category": "Particle",
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"entity": "slowing-down"
}
]
}
]
},
{
"abstract": "Abstract This is an overview of the theoretical understanding of the so-called isotope effect in JET hydrogen versus deuterium plasmas. Experimentally, weak to moderate deviations from naive GyroBohm scaling expectations are found for the core heat transport in L and H-modes. The physical mechanisms behind such deviations are analysed in the framework of the gyrokinetic theory. In the case of particle transport, isotope effects are mostly found in the plasma edge where the density is higher in deuterium than in hydrogen plasmas. In general, both the thermal energy and particle confinement increase with increasing main ion mass. A comparison of such results to expectations for deuterium-tritium plasmas in ITER is discussed.",
"title": "Modelling and theoretical understanding of the isotope effect from JET experiments in view of reliable predictions for deuterium-tritium plasmas",
"URL": "https://research.tue.nl/files/202671330/Garcia_2022_Plasma_Phys._Control._Fusion_64_054001.pdf",
"fields_of_study": [
"Deuterium",
"Plasma",
"Tritium",
"Hydrogen",
"Kinetic isotope effect",
"Jet (fluid)",
"Isotope",
"Scaling",
"Nuclear physics",
"Ion",
"Physics",
"Atomic physics",
"Particle (ecology)",
"Materials science",
"Thermodynamics",
"Oceanography",
"Geometry",
"Mathematics",
"Quantum mechanics",
"Geology"
],
"year_published": 2022,
"first_author": "J Garcia",
"scholarly_citations_count": 9,
"NER-RE": [
{
"sentence": "Abstract This is an overview of the theoretical understanding of the so-called isotope effect in JET hydrogen versus deuterium plasmas.",
"entities": [
{
"category": "Nuclear Fusion Experimental Facility",
"entity": "JET"
},
{
"category": "Chemical Element or Compound",
"entity": "Hydrogen"
},
{
"category": "Chemical Element or Compound",
"entity": "Deuterium"
},
{
"category": "Plasma property",
"entity": "Isotope effect"
}
]
},
{
"sentence": "Experimentally, weak to moderate deviations from naive GyroBohm scaling expectations are found for the core heat transport in L and H-modes.",
"entities": [
{
"category": "Plasma property",
"entity": "H-mode"
},
{
"category": "Plasma property",
"entity": "L-mode"
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{
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"entity": "GyroBohm scaling"
},
{
"category": "Plasma dynamic and behavior",
"entity": "core heat transport"
}
]
},
{
"sentence": "The physical mechanisms behind such deviations are analysed in the framework of the gyrokinetic theory.",
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{
"category": "Theory and Calculation",
"entity": "gyrokinetic theory"
}
]
},
{
"sentence": "In the case of particle transport, isotope effects are mostly found in the plasma edge where the density is higher in deuterium than in hydrogen plasmas.",
"entities": [
{
"category": "Plasma region",
"entity": "plasma edge"
},
{
"category": "Chemical Element or Compound",
"entity": "deuterium"
},
{
"category": "Chemical Element or Compound",
"entity": "hydrogen"
},
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"category": "Plasma property",
"entity": "density"
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"sentence": "In general, both the thermal energy and particle confinement increase with increasing main ion mass.",
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"category": "Particle",
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"entity": "particle confinement"
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"category": "Plasma property",
"entity": "main ion mass"
}
]
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{
"sentence": "A comparison of such results to expectations for deuterium-tritium plasmas in ITER is discussed.",
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{
"category": "Nuclear Fusion Experimental Facility",
"entity": "ITER"
},
{
"category": "Chemical Element or Compound",
"entity": "deuterium"
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{
"category": "Chemical Element or Compound",
"entity": "tritium"
},
{
"category": "Plasma property",
"entity": "deuterium-tritium plasmas"
}
]
}
]
},
{
"abstract": "An experimental study confirms the possibility of initiating nuclear fusion reactions in metal-deuterium targets by bombarding them with ions that are not the reagents of the fusion reaction, in particular, with noble gas ions. The yields of , and , reactions were determined as functions of energy 0.4 to 3.2 MeV and mass of incident ions He, Ne, Ar, Kr, and Xe. It is shown that at ion energies of 0.1 to 1 MeV, the yields of these reactions are rather high 1010 to 107 evention, and they can be increased by raising the incident ion energy, by an appropriate choice of the target. Practical applications of the effect are discussed. 16 refs., 11 figs.",
"title": "Initiation of nuclear fusion reactions in metal-deuterium and metal-deuterium + tritium systems by bombardment with noble gas ions",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST94-A30238",
"fields_of_study": [
"Noble gas",
"Cold fusion",
"Ion",
"Physical chemistry",
"Chemical reaction",
"Nuclear physics",
"Materials science",
"Nuclear reaction",
"Deuterium",
"Tritium",
"Nuclear fusion"
],
"year_published": 1994,
"first_author": "Victor F. Zelensky",
"scholarly_citations_count": 1,
"NER-RE": [
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"sentence": "An experimental study confirms the possibility of initiating nuclear fusion reactions in metal-deuterium targets by bombarding them with ions that are not the reagents of the fusion reaction, in particular, with noble gas ions.",
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"category": "Nuclear Fusion Technique",
"entity": "bombarding with ions"
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{
"category": "Particle",
"entity": "ions"
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{
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"entity": "deuterium"
},
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"entity": "noble gas"
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"entity": "nuclear fusion reactions"
}
]
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"sentence": "The yields of , and , reactions were determined as functions of energy 0.4 to 3.2 MeV and mass of incident ions",
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"sentence": "He, Ne, Ar, Kr, and Xe.",
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{
"category": "Chemical Element or Compound",
"entity": "Ne"
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{
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"entity": "Ar"
},
{
"category": "Chemical Element or Compound",
"entity": "Kr"
},
{
"category": "Chemical Element or Compound",
"entity": "Xe"
}
]
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"entity": "target"
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{
"abstract": "We focus attention on the combinations of swiftly growing electromagnetic instabilities EMI arising in the interaction of relativistic electron beams REB with precompressed deuterium-tritium DT fuels of fast ignition interest for inertial confinement fusion ICF. REB-target system is taken neutral in charge and current with distribution functions including target and beam temperatures. We stress also the significant impact on modes growth rates GR of mode-mode coupling and intrabeam scattering. Collisional damping is documented at large wave numbers in terms of inverse skin depth. A quasi-linear approach yields lower GR than linear ones. One of the most conspicuous output of the linear analysis are three-dimensional 3D broken ridges featuring the largest GR above -space for an oblique propagation .. initial particle beam direction. The given modes are seen immune to any temperature induced damping. Those novel patterns are easily produced by considering simultaneously Weibel, filamentation and two-stream instabilities. The behaviors persist in the presence of smooth density gradients or strong applied magnetic fields. Moreover, in the very early propagation stage with no current neutralization in the presence of large edge density gradients, REB demonstrate a characteristics ringlike and regularly spiked pattern in agreement with recent experimental results and previous simulations.",
"title": "Onset of coherent electromagnetic structures in the relativistic electron beam deuterium-tritium fuel interaction of fast ignition concern",
"URL": "http://ui.adsabs.harvard.edu/abs/2008LPB....26..157D/abstract",
"fields_of_study": [
"Inertial confinement fusion",
"Magnetic field",
"Physics",
"Electron",
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"Atomic physics",
"Relativistic electron beam",
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"first_author": "Claude Deutsch",
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"abstract": "The baseline DT ice layer inertial confinement fusion ICF ignition capsule design requires a hot spot convergence ratio of 34 with a hot spot that is formed from DT mass originally residing in a very thin layer at the inner DT ice surface. In the present paper, we propose alternative ICF capsule designs in which the hot spot is formed mostly or entirely from mass originating within a spherical volume of DT vapor. Simulations of the implosion and hot spot formation in two DT liquid layer ICF capsule conceptsthe DT wetted hydrocarbon CH foam concept and the fast formed liquid FFL conceptare described and compared to simulations of standard DT ice layer capsules. 1D simulations are used to compare the drive requirements, the optimal shock timing, the radial dependence of hot spot specific energy gain, and the hot spot convergence ratio in low vapor pressure DT ice and high vapor pressure DT liquid capsules. 2D simulations are used to compare the relative sensitivities to low-mode -ray flux asymmetries in the DT ice and DT liquid capsules. It is found that the overall thermonuclear yields predicted for DT liquid layer capsules are less than yields predicted for DT ice layer capsules in simulations using comparable capsule size and absorbed energy. However, the wetted foam and FFL designs allow for flexibility in hot spot convergence ratio through the adjustment of the initial cryogenic capsule temperature and, hence, DT vapor density, with a potentially improved robustness to low-mode -ray flux asymmetry.",
"title": "Alternative hot spot formation techniques using liquid deuterium-tritium layer inertial confinement fusion capsules",
"URL": "https://aip.scitation.org/doi/full/10.1063/1.4822342",
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"Physics",
"Cryogenics",
"Atomic physics",
"Vapor pressure",
"Implosion",
"Hot spot (veterinary medicine)",
"Energy source",
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"Vapour density"
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"year_published": 2013,
"first_author": "R. E. Olson",
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"abstract": "The nuclear performance of a fusion-fission hybrid reactor having a molten salt composed of Na-Th-F-Be as the blanket fertile material and operating with a catalyzed deuterium-deuterium DD plasma...",
"title": "NUCLEAR PERFORMANCE OF MOLTEN SALT FUSION-FISSION SYMBIOTIC SYSTEMS FOR CATALYZED DEUTERIUM-DEUTERIUM AND DEUTERIUM-TRITIUM REACTORS.",
"URL": "https://experts.illinois.edu/en/publications/nuclear-performance-of-molten-salt-fusion-fission-symbiotic-syste",
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"abstract": "Radiation-driven, layered deuterium-tritium DT implosions were carried out using 3-shock and 4-shock adiabat-shaped drives and plastic ablators on the National Ignition Facility NIF. The purpose of these shots was to gain further understanding on the relative performance of the low-foot implosions of the National Ignition Campaign versus the subsequent high-foot implosions. The neutron yield performance in the experiment with the 4-shock adiabat-shaped drive was improved by factors 3 to 10, compared to five companion low-foot shots despite large low-mode asymmetries of DT fuel, while measured compression was similar to its low-foot companions. This indicated that the dominant degradation source for low-foot implosions was ablation-front instability growth, since adiabat shaping significantly stabilized this growth. For the experiment with the low-power 3-shock adiabat-shaped drive, the DT fuel compression was significantly increased, by 25 to 36, compared to its companion high-foot implosions. The neutron yield increased by 20, lower than the increase of 50 estimated from one-dimensional scaling, suggesting the importance of residual instabilities and asymmetries. For the experiment with the high-power, 3-shock adiabat-shaped drive, the DT fuel compression was slightly increased by 14 compared to its companion high-foot experiments. However, the compression was reduced compared to the lower-power 3-shock adiabat-shaped drive, correlated with the increase of hot electrons that hypothetically can be responsible for reduced compression in high-power adiabat-shaped experiments as well as in high-foot experiments. The total neutron yield in the high-power 3-shock adiabat-shaped shot N150416 was 8.5 1015 0.2 1015, with the fuel areal density of 0.90 0.07 gcm2, corresponding to the ignition threshold factor parameter IFTX calculated without alpha heating of 0.34 0.03 and the yield amplification due to the alpha heating of 2.4 0.2. The performance parameters were among the highest of all shots on NIF and the closest to ignition at this time, based on the IFTX metric. The follow-up experiments were proposed to continue testing physics hypotheses, to measure implosion reproducibility, and to improve quantitative understanding on present implosion results.",
"title": "Experimental results of radiation-driven, layered deuterium-tritium implosions with adiabat-shaped drives at the National Ignition Facility",
"URL": "https://aip.scitation.org/doi/10.1063/1.4964919",
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"Yield (engineering)",
"Radiation",
"Ignition system",
"Nuclear physics",
"Area density",
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"first_author": "V. A. Smalyuk",
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"abstract": "In the Tokamak Fusion Test Reactor TFTR a substantial improvement in fusion performance has been realized by combining the enhanced confinement due to tritium fueling with the enhanced confinement due to extensive conditioning of the limiter with lithium. This combination has resulted in not only significantly higher global energy confinement times than have previously been obtained in high current supershots, but also in the highest central ratio of thermonuclear fusion output power to input power observed to date.",
"title": "Enhanced performance of deuterium–tritium‐fueled supershots using extensive lithium conditioning in the Tokamak Fusion Test Reactor",
"URL": "https://aip.scitation.org/doi/full/10.1063/1.871050",
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"abstract": "The deuterium-tritium D-T and deuterium-deuterium neutron yield ratio in cryogenic inertial confinement fusion ICF experiments is used to examine multifluid effects, traditionally not included in ICF modeling. This ratio has been measured for ignition-scalable direct-drive cryogenic DT implosions at the Omega Laser Facility using a high-dynamic-range neutron time-of-flight spectrometer. The experimentally inferred yield ratio is consistent with both the calculated values of the nuclear reaction rates and the measured preshot target-fuel composition. These observations indicate that the physical mechanisms that have been proposed to alter the fuel composition, such as species separation of the hydrogen isotopes, are not significant during the period of peak neutron production in ignition-scalable cryogenic direct-drive DT implosions.",
"title": "First Measurements of Deuterium-Tritium and Deuterium-Deuterium Fusion Reaction Yields in Ignition-Scalable Direct-Drive Implosions.",
"URL": "https://inis.iaea.org/search/search.aspx?orig_q=RN:48058868",
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"Atomic physics",
"Nuclear physics",
"Materials science",
"Nuclear reaction",
"Spectrometer",
"Hydrogen",
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"Tritium"
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"year_published": 2017,
"first_author": "Chad Forrest",
"scholarly_citations_count": 9,
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"abstract": "AbstractWe focus attention on the combinations of swiftly growing electromagnetic instabilities EMI arising in the interaction of relativistic electron beams REB with precompressed deuterium-tritium DT fuels of fast ignition interest for inertial confinement fusion ICF. REB-target system is taken neutral in charge and current with distribution functions including target and beam temperatures. We stress also the significant impact on modes growth rates GR of mode-mode coupling and intrabeam scattering. Collisional damping is documented at large wave numbers in terms of inverse skin depth. A quasi-linear approach yields lower GR than linear ones. One of the most conspicuous output of the linear analysis are three-dimensional 3D broken ridges featuring the largest GR above -space for an oblique propagation .. initial particle beam direction. The given modes are seen immune to any temperature induced damping. Those novel patterns are easily produced by considering simultaneously Weibel, filamentation and two-stream instabilities. The behaviors persist in the presence of smooth density gradients or strong applied magnetic fields. Moreover, in the very early propagation stage with no current neutralization in the presence of large edge density gradients, REB demonstrate a characteristics ringlike and regularly spiked pattern in agreement with recent experimental results and previous simulations.",
"title": "Onset of coherent electromagnetic structures in the relativistic electron beam deuterium-tritium fuel interaction of fast ignition concern",
"URL": "NaN",
"fields_of_study": [
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"Beam (structure)",
"Inertial confinement fusion",
"Atomic physics",
"Deuterium",
"Relativistic electron beam",
"Electron",
"Nuclear physics",
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"year_published": 2008,
"first_author": "C. Deutsch",
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"abstract": "Doppler-free two-photon excitation of fluorescence may be used to measure the deuteriumtritium fuel mix in magnetic confinement fusion plasmas. Two atomic transition schemes of the hydrogen isotopes come into question for this purpose I excitation of the first excited energy level n2 and observation of Lyman-α, II excitation of the second excited energy level n3 and observation of Balmer-α. Comparison of the two schemes indicates that both may have their merits in particular situations. Due to lack of information about the future laser characteristics achievable for scheme II, the detailed performance of this scheme cannot yet be definitely assessed.",
"title": "Measurement of the deuterium/tritium fuel mixture in magnetic confinement fusion plasmas by Doppler-free two-photon spectroscopy",
"URL": "http://ui.adsabs.harvard.edu/abs/1999RScI...70..928V/abstract",
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"abstract": "Knowledge of the dynamics and concentration of impurities in the plasma core is crucial to the development of a deuteriumtritium DT tokamak fusion reactor. In this article, we first describe an advanced diagnostic technique to measure the impurities, thermalized helium density, and the deuterium-to-tritium density ratio in DT-burning plasmas. The measurement is made by small-angle collective Thomson scattering using a high-power pulsed CO2 laser and heterodyne receiver system. The component of scattered laser power nearly perpendicular to the magnetic field gives rise to ion cyclotron modulation of the scattered spectrum. Scattered spectrum of expected impurities Ar, Be, and He ash are presented for the International Thermonuclear Experimental Reactor plasmas. The method for the determination of the helium ash density and deuterium-to-tritium ratio are also proposed. Modulation spectra as a function of frequency for different magnetic-field angles are confirmed. Experimental requirements to measure a...",
"title": "Advanced impurity measurement for deuterium–tritium-burning plasmas using pulsed CO2 laser collective Thomson scattering",
"URL": "https://ui.adsabs.harvard.edu/abs/2000RScI...71.3718L/abstract",
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"Light scattering",
"Atomic physics",
"Materials science",
"Laser power scaling",
"Thomson scattering",
"Plasma diagnostics",
"Helium",
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"first_author": "S. Lee",
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"abstract": "Dedicated nuclear diagnostics have been designed, developed, and built within EUROFUSION enhancement programs in the last ten years for installation at the Joint European Torus and capable of operation in high power Deuterium-Tritium DT plasmas. The recent DT Experiment campaign, called DTE2, has been successfully carried out in the second half of 2021 and provides a unique opportunity to evaluate the performance of the new nuclear diagnostics and for an understanding of their behavior in the record high 14 MeV neutron yields up to 4.7 1018 ns and total number of neutrons up to 2 1019 achieved on a tokamak. In this work, we will focus on the 14 MeV high resolution neutron spectrometers based on artificial diamonds which, for the first time, have extensively been used to measure 14 MeV DT neutron spectra with unprecedented energy resolution Full Width at Half Maximum of 1 at 14 MeV. The work will describe their long-term stability and operation over the DTE2 campaign as well as their performance as neutron spectrometers in terms of achieved energy resolution and high rate capability. This important experience will be used to outline the concept of a spectroscopic neutron camera for the SPARC tokamak. The proposed neutron camera will be the first one to feature the dual capability to measure the 2.5 and 14 MeV neutron emissivity profile via the conventional neutron detectors based on liquid or plastics scintillators and ii the 14 MeV neutron spectral emission via the use of high-resolution diamond-based spectrometers. The new opportunities opened by the spectroscopic neutron camera to measure plasma parameters will be discussed.",
"title": "A high-resolution neutron spectroscopic camera for the SPARC tokamak based on the Jet European Torus deuterium-tritium experience.",
"URL": "NaN",
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"year_published": 2022,
"first_author": "M Tardocchi",
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{
"abstract": "For the purpose of investigating fusion-produced neutron effects on semiconductor -ray detectors, detection characteristics of -ray tomography detectors used before and after deuteriumtritium DT andor DD fusion-plasma experiments in the Joint European Torus JET tokamak are studied using synchrotron radiation from a 2.5 GeV positron storage ring at the Photon Factory. Degradations in the responses after neutron exposure into the detectors are found to have functional dependence on -ray energy. Changes in the depletion thicknesses of the detectors are investigated by means of impedance analyses. The Fusion Neutronics Source FNS facility of the Japan Atomic Energy Research Institute is also employed for well calibrated DT fusion-produced neutron irradiation onto these semiconductor -ray detectors. Recovery of the response degradation is found due to a method for supplying the operational bias to the degraded detector. Our theory is applied to interpret these detector characteristics under the irr...",
"title": "Investigation of x-ray-energy responses of semiconductor detectors under deuterium-tritium fusion-produced neutron irradiation",
"URL": "https://scitation.aip.org/content/aip/journal/rsi/72/1/10.1063/1.1319872",
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"category": "Chemical Element or Compound",
"entity": "DT"
}
]
},
{
"sentence": "Recovery of the response degradation is found due to a method for supplying the operational bias to the degraded detector.",
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"category": "Detection and Monitoring Systems",
"entity": "detector"
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"category": "Nuclear Fusion System Component",
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{
"sentence": "Our theory is applied to interpret these detector characteristics under the irr...",
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{
"abstract": "An upper limit for the pumping speed of deuterium D on 77 K surfaces has been determined by in situ pressure measurements in a TFTR neutral beam line pumped by 423 m2 of liquidnitrogencooled cryopanels. The measurement has importance for estimating the tritium T retention in the beam line following operation of the ion sources with tritium. No D2 pumping was observed. An upper limit for D2 pumping on 77 K surfaces of 2.4107 ls cm2 was determined, corresponding to a D2 sticking coefficient of 1.5108. Based on the upper limit a DT retention factor, equal to the ratio of retained DT to DT input, has been determined to be 5103. This upper limit for DT retention bounds the tritium inventory within the beam line to a small fraction of the tritium throughput. Comparably small upper limits for hydrogenic sticking coefficients, of the order of 106 to 1010, have been determined from a review of H2O cryotrapping measurements at 77 K and from the physical adsorption studies of H2 on H2O at 4 K.",
"title": "Deuterium pumping speed measurements on 77 K cryopanels and implications for deuterium–tritium retention in neutral beam systems",
"URL": "http://www.osti.gov/scitech/biblio/6316948-deuterium-pumping-speed-measurements-cryopanels-implications-deuterium-tritium-retention-neutral-beam-systems",
"fields_of_study": [
"Ion",
"Isotope",
"Beam (structure)",
"Atomic physics",
"Nuclear physics",
"Chemistry",
"Stable isotope ratio",
"Deuterium",
"Tritium",
"Pressure measurement",
"Sticking coefficient"
],
"year_published": 1989,
"first_author": "H. F. Dylla",
"scholarly_citations_count": "NaN",
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"abstract": "Implosions of direct-drive, deuteriumtritium DT gas-filled plastic capsules are studied using nuclear diagnostics at the OMEGA laser facility. In addition to traditional neutron measurements, comprehensive sets of spectra of deuterons, tritons, and protons elastically scattered from the fuel and shell by primary DT neutrons knock-on particles are, for the first time, obtained and used for characterizing target performance. It is shown with these measurements that, for 15-atm DT capsules with 20-μm CH shells, improvement of target performance is achieved when on-target irradiation nonuniformity is reduced. Specifically, with a two-dimensional 2D single-color-cycle, 1-THz-bandwidth smoothing by spectral dispersion SSD, plus polarization smoothing PS, a primary neutron yield of 11013, a fuel areal density of 15 mgcm2, and a shell areal density of 60 mgcm2 are obtained these are, respectively, 80, 60, and 35 higher than those achieved using 0.35-THz, 3-color-cycle, 2D SSD without PS. In determining fuel areal density we assume the fuel to have equal numbers of D and T. With full beam smoothing, implosions with moderate radial convergence 1015 are shown to have ρR performance close to one-dimensional-code predictions, but a ratio of measured-to-predicted primary neutron yield of 0.3. Other capsules that are predicted to have much higher radial convergence 3.8-atm DT gas with 20-μm CH shell are shown to have ρRfuel3 mgcm2, falling short of prediction by about a factor of 5. The corresponding convergence ratios are similar to the values for 15-atm capsules. This indicates, not surprisingly, that the effects of mix are more deleterious for high-convergence implosions. A brief comparison of these moderate- and high-convergence implosions to those of similar deuteriumdeuterium D2 gas-filled capsules shows comparable hydrodynamic performance.",
"title": "Study of direct-drive, deuterium–tritium gas-filled plastic capsule implosions using nuclear diagnostics at OMEGA",
"URL": "https://researchbank.swinburne.edu.au/items/5eee18bd-2f81-4fea-9044-dda9af7459c0/1/",
"fields_of_study": [
"Irradiation",
"Physics",
"Neutron",
"Atomic physics",
"Area density",
"Omega",
"Plasma diagnostics",
"Nuclear magnetic resonance",
"Spectral line",
"Deuterium",
"Tritium illumination"
],
"year_published": 2001,
"first_author": "C. K. Li",
"scholarly_citations_count": 46,
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"sentence": "In determining fuel areal density we assume the fuel to have equal numbers of D and T. With full beam smoothing, implosions with moderate radial convergence 1015 are shown to have ρR performance close to one-dimensional-code predictions, but a ratio of measured-to-predicted primary neutron yield of 0.3.",
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"sentence": "This indicates, not surprisingly, that the effects of mix are more deleterious for high-convergence implosions.",
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{
"abstract": "Compression and ignition of deuteriumtritium fuel under conditions relevant to the scheme of fast ignition by laser generated proton beams are studied by numerical simulation. Compression of a fuel containing spherical capsule driven by a pulse of thermal radiation is studied by a one-dimensional radiation hydrodynamics code. Irradiation of the compressed fuel by an intense proton beam, generated by a target at distance from the capsule center, and subsequent ignition and burn are simulated by a two-dimensional code. A robust capsule, absorbing 635 kJ of 210 eV peak thermal rays, with fusion yield of almost 500 MJ, has been designed, which could allow for target gain of 200. On the other hand, for a reasonable proton spectrum the required proton beam energy Eig, exceeds 25 kJ for d4 mm, even neglecting beam losses in the hohlraum and assuming that the beam can be focused on a spot with radius of 10 μm. The effects of proton range lengthening due to...",
"title": "Numerical study of fast ignition of ablatively imploded deuterium–tritium fusion capsules by ultra-intense proton beams",
"URL": "https://ui.adsabs.harvard.edu/abs/2002PhPl....9.3098T/abstract",
"fields_of_study": [
"Irradiation",
"Physics",
"Ignition system",
"Beam (structure)",
"Atomic physics",
"Range (particle radiation)",
"Laser",
"Hohlraum",
"Proton",
"Thermal radiation"
],
"year_published": 2002,
"first_author": "Mauro Temporal",
"scholarly_citations_count": 162,
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{
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]
},
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},
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"category": "Physical Process",
"entity": "fuel"
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"sentence": "Irradiation of the compressed fuel by an intense proton beam, generated by a target at distance from the capsule center, and subsequent ignition and burn are simulated by a two-dimensional code.",
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"entity": "target"
},
{
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"entity": "two-dimensional code"
},
{
"category": "Physical Process",
"entity": "irradiation"
},
{
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"entity": "ignition"
},
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"entity": "burn"
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{
"abstract": "Fusion neutronics experiments are performed on a full-coverage blanket with various configurations of a beryllium neutron multiplier. In the basic experimental system, a lithium carbonate enclosure contains a lithium oxide test zone and a deuterium-tritium neutron source to simulate a neutron spectrum in a fusion reactor. Five beryllium configurations are adopted to examine the effects of neutron multiplication and reflection by beryllium. The measurements are carried out along the central line in the test zone. Various measurement techniques are applied to obtain the tritium production rate distribution, which is one of the most important parameters for assessing the total tritium breeding ratio in a fusion blanket. In addition, the reaction rates and the neutron spectrum are measured to provide test data for confirmation of calculation results. These data are compared among six different configurations of the experimental system. Consistency between the different techniques for each measured parameter is also tested among different experimental systems. The experimental results are compared with the calculations by DOT 3.5 using JENDL-3PRI and PR2. The calculation differs from the experimental data by 10, except for the beryllium zone.",
"title": "Neutronics Integral Experiments of Simulated Fusion Reactor Blanket with Various Beryllium Configurations Using Deuterium-Tritium Neutrons",
"URL": "https://www.ans.org/pubs/journals/fst/a_30646",
"fields_of_study": [
"Neutron",
"Neutron source",
"Nuclear physics",
"Materials science",
"Fusion power",
"Blanket",
"Beryllium",
"Deuterium",
"Tritium",
"Neutron transport"
],
"year_published": 1995,
"first_author": "Chikara Konno",
"scholarly_citations_count": 1,
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{
"abstract": "To meet urgent requirements for data validation, an experimental analysis has been carried out for isotopic radioactivity induced by deuterium-tritium neutron irradiation in structural materials. The primary objective is to examine the adequacy of the activation cross sections implemented in the current activation calculation codes considered for use in fusion reactor nuclear design. Four activation cross-section libraries, namely, JENDL, LIB90, REAC 63, and REAC 175 were investigated in this current analysis. The isotopic induced radioactivity calculations using these four libraries are compared with experimental values obtained in the Japan Atomic Energy Research InstituteU.S. Department of Energy collaborative program on fusion blanket neutronics. The nine materials studied are aluminum, silicon, titanium, vanadium, chromium, MnCu alloy, iron, nickel, niobium, and Type 316 stainless steel. The adequacy of the cross sections is investigated through the calculation to experiment analysis. As a result, most of the discrepancies in the calculations from experiments can be explained by inadequate activation cross sections. In addition, uncertainties due to neutron energy groups and neutron transport calculation are considered. The JENDL library gives the best agreement with experiments, followed by REAC 175, LIB90, and REAC 63, in this order. Clear suggestions for a future direction to improve the overall calculation accuracy are developed based on the current experimental analysis.",
"title": "Measurements and Analyses of Decay Radioactivity Induced in Simulated Deuterium-Tritium Neutron Environments for Fusion Reactor Structural Materials",
"URL": "https://www.ans.org/pubs/journals/fst/a_30402",
"fields_of_study": [
"Neutron",
"Nuclear physics",
"Materials science",
"Induced radioactivity",
"Fusion power",
"Neutron temperature",
"Blanket",
"Deuterium",
"Tritium",
"Neutron transport"
],
"year_published": 1995,
"first_author": "Y. Ikeda",
"scholarly_citations_count": 12,
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"abstract": "Accurate knowledge of the properties of warm dense deuteriumtritium DT is essential to reliably design inertial confinement fusion ICF implosions. In the warm-dense-matter regime, routinely accessed by low-adiabat ICF implosions,1 strongcoupling and degeneracy effects play an important role in determining plasma properties. Using first-principles methods of both path-integral Monte Carlo and quantum molecular-dynamics QMD, we have performed systematic investigation of the equation of state,2 thermal conductivity,3 4 5 and opacity6 for DT over a wide range of densities and temperatures. These first-principles properties have been incorporated into our hydrocodes. When compared to hydro simulations using standard plasma models, significant differences in 1-D target performance have been identified for simulations of DT implosions. For low-adiabat α 2 DT plasma conditions, the QMD-predicted opacities are 10 to 100 higher than predicted by the coldopacitypatched astrophysical opacity table. The thermal conductivity could be 3 to 10 larger than the LeeMore model prediction. These enhancements can modify the shell adiabat and shock dynamics in lower-α ICF implosions, which could lead to 40 variations in peak density and neutron yield. This material is based upon work supported by the Department of Energy National Nuclear Security Administration under Award Number DE-NA0001944.",
"title": "Impact of First-Principles Property Calculations of Warm-Dense Deuterium/Tritium on Inertial Confinement Fusion Target Designs",
"URL": "https://ui.adsabs.harvard.edu/abs/2014APS..DPPTI2003H/abstract",
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"Physics",
"Lawson criterion",
"Nuclear physics",
"Monte Carlo method",
"Equation of state",
"Deuterium",
"Opacity",
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"abstract": "We have studied the effectiveness of beta heating on driving a deuteriumtritium DT ice layer toward uniformity within spherical inertial fusion targets. Beta heating results from the deposition of energy from the beta particles from the tritium decay in these targets. These targets are enclosed in a constant temperature environment. This study first considered a onedimensional heat transfer model of an idealized target, geometry, and environment. We concluded that beta energy deposition can drive a nonuniform DT ice layer towards uniformity. The maximum rate at which this redistribution can occur is given by dδdtδδθTC, where δDT ice thickness in excess of that for a uniform layer and θTCa time constant 1500 . This translates to a factor of 10 reduction in nonuniformity every hour. We also evaluated, and continue to do so, the consequences of deviations from the idealized case assumptions and the selection of certain experimental parameters, on the actual behavior of DT ice in such cryogenic targets. The status of this work is such that we have confidence in the use of beta heating to drive the DT ice toward uniformity for reactorsize targets 1 mm and larger in diameter.",
"title": "Beta energy driven uniform deuterium--tritium ice layer in reactor-size cryogenic inertial fusion targets",
"URL": "https://scitation.aip.org/content/avs/journal/jvsta/6/3/10.1116/1.575234",
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"Beta particle",
"Cryogenics",
"Atomic physics",
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"Charged particle",
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"abstract": "In deuterium-tritium cryogenic implosions, hot-spot -ray self-emission is observed to begin at a larger shell radius than is predicted by a one-dimensional radiation-hydrodynamic implosion model. Laser-imprint is shown to explain the observation for a low-adiabat implosion. For more-stable implosions the data are not described by the imprint model and suggest there are additional sources of decompression of the dense fuel.",
"title": "Observations of anomalous x-ray emission at early stages of hot-spot formation in deuterium-tritium cryogenic implosions",
"URL": "https://ui.adsabs.harvard.edu/abs/2021PhRvE.103b3201S/abstract",
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"X-ray",
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"abstract": "Experiments have been performed on the TFTR to study rf wave heating of a D-T plasma by way of the second-harmonic tritium cyclotron resonance. The addition of tritium ions to a deuterium plasma allows for absorption of the rf waves at the tritium cyclotron harmonics and by electron damping of a mode converted ion Bernstein wave. Competing mechanisms include direct electron damping and damping at the fundamental cyclotron resonance of deuterium, particles, and He ions. The contribution of each is estimated from a series of plasma discharges where various plasma parameters are varied. The majority of the rf power is found to damp on the tritium ions.",
"title": "Ion cyclotron range of frequency heating of a deuterium-tritium plasma via the second-harmonic tritium cyclotron resonance.",
"URL": "https://ui.adsabs.harvard.edu/abs/1995PhRvL..75..842W/abstract",
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"Fourier transform ion cyclotron resonance",
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"abstract": "Determining fuel areal density ρR in moderate-ρR 100200 mgcm2 cryogenic deuterium-tritium DT implosions is challenging as it requires new spectrometry techniques and analysis methods to be developed. In this paper, we describe a new method for analyzing the spectrum of knock-on deuterons KO-Ds, elastically scattered by primary DT neutrons, from which a fuel ρR can be inferred for values up to 200 mgcm2. This new analysis method, which uses Monte Carlo modeling of a cryogenic DT implosion, improves significantly the previous analysis method in two fundamental ways. First, it is not affected by significant spatial-yield variations, which degrade the diagnosis of the fuel ρR spatial yield variations of about 20 are typically observed, and second, it does not break down when the fuel ρR exceeds 70 mgcm2.",
"title": "Diagnosing fuel ρR and ρR asymmetries in cryogenic deuterium-tritium implosions using charged-particle spectrometry at OMEGA",
"URL": "http://scitation.aip.org/content/aip/journal/pop/16/4/10.1063/1.3098540",
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"abstract": "The toroidal Alfven eigenmodes TAE in the Tokamak Fusion Test Reactor deuterium-tritium plasmas are analyzed using the NOVA-K code. The theoretical results are compared with the experimental measurements in detail. In most cases, the theory agrees with the observations in terms of mode frequency, mode structure, and mode stability. However, one mode with toroidal mode number 2 is observed to be poloidally localized on the high field side of the magnetic axis with a mode frequency substantially below the TAE frequency.",
"title": "Alpha particle-driven toroidal Alfvén eigenmodes in Tokamak Fusion Test Reactor deuterium–tritium plasmas: Theory and experiments",
"URL": "https://scitation.aip.org/content/aip/journal/pop/5/12/10.1063/1.873165",
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"Atomic physics",
"Tokamak Fusion Test Reactor",
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"year_published": 1998,
"first_author": "Guoyong Fu",
"scholarly_citations_count": 22,
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"abstract": "First simultaneous measurements of deuterium-deuterium DD and deuterium-tritium neutrons from deuterium plasmas using a Single crystal Diamond Detector are presented in this paper. The measurements were performed at JET with a dedicated electronic chain that combined high count rate capabilities and high energy resolution. The deposited energy spectrum from DD neutrons was successfully reproduced by means of Monte Carlo calculations of the detector response function and simulations of neutron emission from the plasma, including background contributions. The reported results are of relevance for the development of compact neutron detectors with spectroscopy capabilities for installation in camera systems of present and future high power fusion experiments.",
"title": "Single crystal diamond detector measurements of deuterium-deuterium and deuterium-tritium neutrons in Joint European Torus fusion plasmas.",
"URL": "https://boa.unimib.it/handle/10281/59048",
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"abstract": "In this work, the performance of fusion reactor ITER90H-P with considering DT and D-3He fuels are examined by writing the dynamics equations on the system reactor. Therefore, we solve these equations analytically in the steady state. In this state we determine the optimum conditions for achieving the maximum fusion gain.In addition, we ignore the impurities because we need to high performance points without impurities. Our calculations in this paper show that we have maximum fusion gain for DT and D-3He fusion reactions in steady state at resonance temperature Kev70 for D-T fusion reaction respectively.Their maximum values of fusion gain are equal to 6.01 for D-T fuel-andthe0.012 for D-3He, respectively. Therefore, currently, using D-3He as a fusion fuel is not recommended.",
"title": "Scrutiny on the Static Behavior of Physical Parameters for ITER90H-P Fusion Reactor Using Deuterium-Tritium and Deuterium-Helium Mixtures",
"URL": "https://core.ac.uk/display/103683392",
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"abstract": "The most performant deuterium-tritium DT plasma discharges realized by the Joint European Torus JET tokamak in the recent DT campaign have produced neutron yields on the order of 1018 ns. At such high neutron yields, gamma-ray spectroscopy measurements with scintillators are challenging as events from the neutron-induced background often dominate over the signal, leading to a significant fraction of pileup events and instability of the photodetector gain along with the consequent degradation of the reconstructed spectrum. Here, we describe the solutions adopted for the tangential lanthanum bromide spectrometer installed at JET. A data acquisition system with free streaming mode digitization capabilities for the entire duration of the discharge has been used to solve dead-time related issues and a data reconstruction code with pileup recovery and photodetector gain drift restoration has been implemented for off-line analysis of the data. This work focuses on the acquired data storage and parsing, with a detailed explanation of the pileup recovery and gain drift restoration algorithms.",
"title": "A new dedicated signal processing system for gamma-ray spectrometers in high power deuterium-tritium plasma scenarios in tokamaks.",
"URL": "NaN",
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"year_published": 2022,
"first_author": "G Marcer",
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"abstract": "An accurate calibration of the JET neutron diagnostics with a 14 MeV neutron generator was performed in the first half of 2017 in order to provide a reliable measurement of the fusion power during the next JET deuterium-tritium DT campaign. In order to meet the target accuracy, the chosen neutron generator has been fully characterized at the Neutron Metrology Laboratory of the National Physical Laboratory NPL, Teddington, United Kingdom. The present paper describes the measurements of the neutron energy spectra obtained using a high-resolution single-crystal diamond detector SCD. The measurements, together with a new neutron source routine ad hoc developed for the MCNP code, allowed the complex features of the neutron energy spectra resulting from the mixed DT beam ions interacting with the TD target nuclei to be resolved for the first time. From the spectral analysis a quantitative estimation of the beam ion composition has been made. The unprecedented intrinsic energy resolution 1 full width at half maximum FWHM at 14 MeV of diamond detectors opens up new prospects for diagnosing DT plasmas, such as, for instance, the possibility to study non-classical slowing down of the beam ions by neutron spectroscopy on ITER.",
"title": "Neutron spectroscopy measurements of 14 MeV neutrons at unprecedented energy resolution and implications for deuterium-tritium fusion plasma diagnostics",
"URL": "http://ui.adsabs.harvard.edu/abs/2018MeScT..29d5502R/abstract",
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"Neutron temperature",
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"year_published": 2018,
"first_author": "D. Rigamonti",
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{
"abstract": "This paper reconsiders the magneto-inertia confinement approach to fusion in dynamic -pinch with a new method of generating a hot plasma using a frozen deuterium-tritium D-T tube as an initial condition. If modern pulsed power technology can induce the high current of the order of 10 MA along the tube, the dense -pinch plasma formed from the electro-magnetical implosion of thin tubular D-T ice with a radius of about 1 mm can satisfy the Lawson criterion for its 1 cm length.",
"title": "Magneto-Inertia Confinement Approach (MICA) to Fusion in Dynamic Z-Pinch Formed from a Frozen Deuterium-Tritium Tube",
"URL": "http://ci.nii.ac.jp/naid/110000012199",
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"Implosion",
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"year_published": 1987,
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{
"abstract": "A diagnostic method for small non-Maxwellian tails in fuel-ion velocity distribution functions is proposed this method uses the anisotropy of neutron emissions, and it is based on the numerical analysis of the incident fast neutron spectrum on the first wall of a fusion device. Neutron energy spectra are investigated for each incident position along the first wall and each angle of incidence assuming an ITER-like deuteriumtritium plasma it is heated by tangential-neutral-beam injection. Evaluating the incident neutron spectra at all wall positions and angles of incidence enables the selective measurement of non-Gaussian components in the neutron emission spectrum for energetic ion diagnostics in addition, the optimal detector position and orientation can be determined. At the optimal detector position and orientation, the ratio of non-Gaussian components to the Gaussian peak can be two orders of magnitude greater than the ratio in the neutron emission spectrum. This result can improve the accuracy of energetic ion diagnostics in plasmas when small, anisotropic non-Maxwellian tails are formed in fuel ion velocity distribution functions. We focus on the non-Gaussian components greater than 14 MeV, where the effect of the background noise .., slowing-down neutrons by scattering throughout the machine structure can be ignored.A diagnostic method for small non-Maxwellian tails in fuel-ion velocity distribution functions is proposed this method uses the anisotropy of neutron emissions, and it is based on the numerical analysis of the incident fast neutron spectrum on the first wall of a fusion device. Neutron energy spectra are investigated for each incident position along the first wall and each angle of incidence assuming an ITER-like deuteriumtritium plasma it is heated by tangential-neutral-beam injection. Evaluating the incident neutron spectra at all wall positions and angles of incidence enables the selective measurement of non-Gaussian components in the neutron emission spectrum for energetic ion diagnostics in addition, the optimal detector position and orientation can be determined. At the optimal detector position and orientation, the ratio of non-Gaussian components to the Gaussian peak can be two orders of magnitude greater than the ratio in the neutron emission spectrum. This result can improve the accuracy of...",
"title": "Incident neutron spectra on the first wall and their application to energetic ion diagnostics in beam-injected deuterium–tritium tokamak plasmas",
"URL": "https://kyushu-u.pure.elsevier.com/ja/publications/incident-neutron-spectra-on-the-first-wall-and-their-application-",
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"Neutron emission",
"Atomic physics",
"Distribution function",
"Scattering",
"Neutron temperature",
"Angle of incidence (optics)",
"Plasma diagnostics",
"Spectral line"
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"year_published": 2017,
"first_author": "Shota Sugiyama",
"scholarly_citations_count": 13,
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"category": "Particle",
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"category": "Nuclear Fusion Device Type",
"entity": "fusion device"
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"category": "Concept",
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"category": "Theory and Calculation",
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"entity": "incident fast neutron spectrum"
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"sentence": "Neutron energy spectra are investigated for each incident position along the first wall and each angle of incidence assuming an ITER-like deuteriumtritium plasma it is heated by tangential-neutral-beam injection.",
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"category": "Nuclear Fusion Experimental Facility",
"entity": "ITER"
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"entity": "neutron"
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{
"category": "Particle",
"entity": "deuterium"
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{
"category": "Particle",
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"category": "Plasma property",
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{
"sentence": "Evaluating the incident neutron spectra at all wall positions and angles of incidence enables the selective measurement of non-Gaussian components in the neutron emission spectrum for energetic ion diagnostics in addition, the optimal detector position and orientation can be determined.",
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"category": "Nuclear Fusion System Component",
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"sentence": "At the optimal detector position and orientation, the ratio of non-Gaussian components to the Gaussian peak can be two orders of magnitude greater than the ratio in the neutron emission spectrum.",
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"category": "Detection and Monitoring Systems",
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"category": "Plasma property",
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"sentence": "This result can improve the accuracy of energetic ion diagnostics in plasmas when small, anisotropic non-Maxwellian tails are formed in fuel ion velocity distribution functions.",
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{
"category": "Plasma property",
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"sentence": "We focus on the non-Gaussian components greater than 14 MeV, where the effect of the background noise .., slowing-down neutrons by scattering throughout the machine structure can be ignored.",
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"category": "Nuclear Fusion System Component",
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{
"sentence": "A diagnostic method for small non-Maxwellian tails in fuel-ion velocity distribution functions is proposed this method uses the anisotropy of neutron emissions, and it is based on the numerical analysis of the incident fast neutron spectrum on the first wall of a fusion device.",
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"category": "Nuclear Fusion System Component",
"entity": "first wall"
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"category": "Detection and Monitoring Systems",
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"category": "Nuclear Fusion Experimental Facility",
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"entity": "neutron"
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{
"category": "Particle",
"entity": "deuterium"
},
{
"category": "Particle",
"entity": "tritium"
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{
"category": "Nuclear Fusion Technique",
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"category": "Plasma property",
"entity": "plasma"
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{
"sentence": "Evaluating the incident neutron spectra at all wall positions and angles of incidence enables the selective measurement of non-Gaussian components in the neutron emission spectrum for energetic ion diagnostics in addition, the optimal detector position and orientation can be determined.",
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"category": "Nuclear Fusion System Component",
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"sentence": "At the optimal detector position and orientation, the ratio of non-Gaussian components to the Gaussian peak can be two orders of magnitude greater than the ratio in the neutron emission spectrum.",
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"sentence": "This result can improve the accuracy of...",
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{
"abstract": "Summary One of the most important parameters in the design of the fusion-fission hybrid reactor is the selection of the first wall material. Because the oxide dispersion-strengthened ODS steel alloys have high temperature oxidation, high radiation resistance, good hardness, and corrosion resistance properties, they are thought first wall candidate materials for fusion and fission applications. The objective of this paper is to determine the best radiation damage parameters of various experimental and commercial ODS steels namely, 12Y1, 12YWT, 1DS, IDK, Eurofer97, MA956, MA957, and PM 2000. Neutron spectrum and average neutron energy throughout blanket, displacement per atom, hydrogen and helium production, nuclear heating, and tritium breeding ratio were calculated by using Monte Carlo methods with Monte Carlo neutron-photon transport code and nuclear libraries named as ENDFB-VI and CLAW-IV. It is assumed that calculated reactor has been operated full power during a year and neutron wall load is 2.25 MWm2 1014 ns. All investigated first wall materials should be replaced between 3.5 and 4 years. All investigated materials provide minimum required tritium breeding ratio value, and when considering all the calculations performed in this work, 1DS ODS steel is the most suitable first wall materials with respect to other investigated ODS steels.",
"title": "Evaluation of the radiation damage parameters of ODS steel alloys in the first wall of deuterium‐tritium fusion‐fission (hybrid) reactors",
"URL": "https://onlinelibrary.wiley.com/doi/full/10.1002/er.3782",
"fields_of_study": [
"Nuclear engineering",
"Neutron",
"Radiation damage",
"Radiochemistry",
"Materials science",
"Neutron temperature",
"Hybrid reactor",
"Blanket",
"Hydrogen",
"Deuterium",
"Neutron flux"
],
"year_published": 2017,
"first_author": "Güven Tunç",
"scholarly_citations_count": 5,
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"sentence": "Summary One of the most important parameters in the design of the fusion-fission hybrid reactor is the selection of the first wall material.",
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"sentence": "Because the oxide dispersion-strengthened ODS steel alloys have high temperature oxidation, high radiation resistance, good hardness, and corrosion resistance properties, they are thought first wall candidate materials for fusion and fission applications.",
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"sentence": "The objective of this paper is to determine the best radiation damage parameters of various experimental and commercial ODS steels namely, 12Y1, 12YWT, 1DS, IDK, Eurofer97, MA956, MA957, and PM 2000.",
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"category": "Chemical Element or Compound",
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"sentence": "Neutron spectrum and average neutron energy throughout blanket, displacement per atom, hydrogen and helium production, nuclear heating, and tritium breeding ratio were calculated by using Monte Carlo methods with Monte Carlo neutron-photon transport code and nuclear libraries named as ENDFB-VI and CLAW-IV.",
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"category": "Database",
"entity": "ENDFB-VI"
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{
"category": "Database",
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{
"category": "Particle",
"entity": "neutron"
},
{
"category": "Particle",
"entity": "photon"
},
{
"category": "Chemical Element or Compound",
"entity": "hydrogen"
},
{
"category": "Chemical Element or Compound",
"entity": "helium"
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{
"category": "Chemical Element or Compound",
"entity": "tritium"
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{
"category": "Physics Entity",
"entity": "neutron energy"
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{
"category": "Physics Entity",
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"category": "Plasma property",
"entity": "displacement per atom"
}
]
},
{
"sentence": "It is assumed that calculated reactor has been operated full power during a year and neutron wall load is 2.25 MWm2 1014 ns.",
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"category": "Nuclear Fusion System Component",
"entity": "neutron wall"
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"category": "Time reference",
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"entity": "neutron wall load"
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{
"category": "Nuclear Fusion System Configuration",
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"category": "Nuclear Fusion System Configuration",
"entity": "full power"
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]
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{
"sentence": "All investigated first wall materials should be replaced between 3.5 and 4 years.",
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"category": "Nuclear Fusion System Component",
"entity": "first wall"
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{
"sentence": "All investigated materials provide minimum required tritium breeding ratio value, and when considering all the calculations performed in this work, 1DS ODS steel is the most suitable first wall materials with respect to other investigated ODS steels.",
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"category": "Nuclear Fusion System Component",
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"entity": "tritium breeding ratio value"
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]
},
{
"abstract": "The influence of capsule wall material and the transfer gas surrounding the capsule on the time required for beta-heating-induced redistribution of a 50-50 mole percent mixture of deuterium and tri...",
"title": "Theory and Numerical Modelling of the Effects of Ablator Wall and Hohlraum Transfer Gas Thermal Resistances on Deuterium-Tritium Redistribution Rates",
"URL": "http://epubs.ans.org/?a=1172",
"fields_of_study": [
"Materials science",
"Thermal",
"Redistribution (chemistry)",
"Wall material",
"Mole fraction",
"Hohlraum",
"Deuterium",
"Tritium",
"Thermodynamics"
],
"year_published": 2006,
"first_author": "Warren H. Giedt",
"scholarly_citations_count": 4,
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{
"abstract": "The work reported herein was conducted in response to an ITER Task to demonstrate experimentally that pulsed and continuous operations of a D-T neutron source lead, in general, to differing impacts...",
"title": "Experimental Demonstration of Differing Impacts of Pulsed and Continuous Operation of a Deuterium-Tritium Neutron Source on Induced Radioactivity in the Context of ITER",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST96-A11963099",
"fields_of_study": [
"Neutron source",
"Nuclear physics",
"Materials science",
"Induced radioactivity",
"Context (language use)",
"Continuous operation",
"Deuterium",
"Tritium"
],
"year_published": 1996,
"first_author": "Anil Kumar",
"scholarly_citations_count": "NaN",
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{
"abstract": "A new tangential gamma-ray spectrometer has been developed for fast ion measurements in deuterium and deuteriumtritium plasmas of the Joint European Torus JET. The instrument is based on a LaBr3 crystal with a photo-multiplier tube and replaces a pre-existing bismuth germanate detector, providing enhanced energy resolution and a counting rate capability in the MHz range. The line of sight is equipped with a LiH attenuator, which reduces the background due to 14 MeV neutron interactions with the crystal by more than two orders of magnitude and enables the observation of gamma-ray emission from confined α particles in JET deuteriumtritium plasmas. Thanks to its tangential line of sight, the detector can distinguish co- and counter-passing ions. The performance of the instrument is demonstrated through the results of recent JET fast ion experiments in deuterium plasmas.",
"title": "A new tangential gamma-ray spectrometer for fast ion measurements in deuterium and deuterium-tritium plasmas of the Joint European Torus.",
"URL": "https://aip.scitation.org/doi/full/10.1063/5.0043806",
"fields_of_study": [
"Jet (fluid)",
"Ion",
"Neutron",
"Atomic physics",
"Materials science",
"Joint European Torus",
"Bismuth germanate",
"Spectrometer",
"Deuterium",
"Plasma"
],
"year_published": 2021,
"first_author": "M. Nocente",
"scholarly_citations_count": 11,
"NER-RE": [
{
"sentence": "A new tangential gamma-ray spectrometer has been developed for fast ion measurements in deuterium and deuteriumtritium plasmas of the Joint European Torus JET.",
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"sentence": "The line of sight is equipped with a LiH attenuator, which reduces the background due to 14 MeV neutron interactions with the crystal by more than two orders of magnitude and enables the observation of gamma-ray emission from confined α particles in JET deuteriumtritium plasmas.",
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{
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{
"sentence": "Thanks to its tangential line of sight, the detector can distinguish co- and counter-passing ions.",
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"sentence": "The performance of the instrument is demonstrated through the results of recent JET fast ion experiments in deuterium plasmas.",
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{
"abstract": "The knock-on tail formations in fuel-ion velocity distribution functions by energetic alpha particles by the Td,n4He reaction and protons by the Dd,pT and 3Hed,p4He reactions are investigated by simultaneously solving the BoltzmannFokkerPlanck BFP equations for deuteron, triton, 3He, alpha particle and proton in an ITER-like DT plasma admixed with a small amount of 3He. As a result of the 3He inclusion, a fraction of the transferred energy from energetic ions to thermal deuterons and tritons via nuclear plus interference NI scattering is reduced. Owing to the NI scattering of the energetic protons by fuel ions, the latter are knocked up to higher energies. The knocking-up effect of fuel ions is enhanced with increasing 3He concentration. It is shown that if 3He with relative concentration of 4.2, .., is included in Te 20keV, ne 9.5 1019m3 plasma, the magnitude of the knock-on tail in deuteron distribution function in 300keV3MeV energy range is reduced by about 15 from the value when 3He is not externally supplied. Such knock-on tail reduction also results in alternation of the non-Gaussian neutron emission spectrum with energies less than 13MeV and above 15MeV.",
"title": "Effect of thermal 3He minorities on knock-on tail formation and the resulting neutron emission spectrum modification in deuterium–tritium plasmas",
"URL": "http://iopscience.iop.org/article/10.1088/0741-3335/53/3/035023/pdf",
"fields_of_study": [
"Physics",
"Ion",
"Neutron emission",
"Atomic physics",
"Distribution function",
"Scattering",
"Proton",
"Deuterium",
"Alpha particle",
"Emission spectrum"
],
"year_published": 2011,
"first_author": "Hideaki Matsuura",
"scholarly_citations_count": 20,
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"abstract": "Beta-layering, the process of beta-decay heat-driven mass redistribution, has been demonstrated in a deuterium-tritium D-T-filled polymer sphere of the type required for fusion ignition experiments at the National Ignition Facility. This is the first report, to the best of the authors knowledge, of a D-T layer formed in a permeation-filled sphere. The 2-mm-diam sphere was filled with D-T by permeation cooled to cryogenic temperatures while in the high-pressure permeation vessel and, while cold, removed to an optical axis where the D-T was frozen, melted, and beta-layered in a series of experiments over several weeks time. This work was performed in the Los Alamos National Laboratory cryogenic pressure loader system. The beta-layering time constant was 24.0 2.5 min, less than the theoretical value of 26.8 min, and not showing the significant increase due to build-up of He often observed in beta-layered samples. Supercooling of the liquid D-T was observed. Neither the polymer target nor its tenting material showed visual signs of degradation after 5 weeks of exposure to D-T. Small external thermal gradients were used to shift the D-T material back and forth within the sphere.",
"title": "Deuterium-tritium beta-layering within a national ignition facility scale polymer target in the lanl cryogenic pressure loader",
"URL": "https://www.ans.org/pubs/journals/fst/a_1078",
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"Inertial confinement fusion",
"Supercooling",
"Analytical chemistry",
"Fusion ignition",
"Cryogenics",
"Nuclear physics",
"Materials science",
"National Ignition Facility",
"Helium-3",
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"year_published": 2005,
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"abstract": "The fuel ion ratio is of central importance for the performance and control of a future burning fusion plasma, and reliable measurements of this quantity are essential for ITER. This...",
"title": "Fuel ion ratio determination in NBI heated deuterium tritium fusion plasmas at JET using neutron emission spectrometry",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/55/2/023005/pdf",
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"abstract": "High Density Carbon or diamond is a promising ablator material for use in near-vacuum hohlraums, as its high density allows for ignition designs with laser pulse durations of 10 ns. A series of Inertial Confinement Fusion ICF experiments in 2013 on the National Ignition Facility culminated in a deuterium-tritium DT layered implosion driven by a 6.8 ns, 2-shock laser pulse. This paper describes these experiments and comparisons with ICF design code simulations. Backlit radiography of a tritium-hydrogen-deuterium THD layered capsule demonstrated an ablator implosion velocity of 385 kms with a slightly oblate hot spot shape. Other diagnostics suggested an asymmetric compressed fuel layer. A streak camera-based hot spot self-emission diagnostic SPIDER showed a double-peaked history of the capsule self-emission. Simulations suggest that this is a signature of low quality hot spot formation. Changes to the laser pulse and pointing for a subsequent DT ...",
"title": "Cryogenic tritium-hydrogen-deuterium and deuterium-tritium layer implosions with high density carbon ablators in near-vacuum hohlraums",
"URL": "https://www.osti.gov/pages/biblio/1184519-cryogenic-thd-dt-layer-implosions-high-density-carbon-ablators-near-vacuum-hohlraums",
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"abstract": "A record fuel hot-spot pressure was inferred from -ray and nuclear diagnostics for direct-drive inertial confinement fusion cryogenic, layered deuterium--tritium implosions on the 60-beam, 30-kJ, 351-nm OMEGA Laser System. When hydrodynamically scaled to the energy of the National Ignition Facility, these implosions achieved a Lawson parameter of the value required for ignition, similar to indirect-drive implosions, and nearly half of the direct-drive ignition-threshold pressure. Relative to symmetric, one-dimensional simulations, the inferred hot-spot pressure is approximately 40 lower. Three-dimensional simulations suggest that low-mode distortion of the hot spot seeded by laser-drive nonuniformity and target-positioning error reduces target performance.",
"title": "Demonstration of Fuel Hot-Spot Pressure in Excess of 50 Gbar for Direct-Drive, Layered Deuterium-Tritium Implosions on OMEGA.",
"URL": "https://jglobal.jst.go.jp/en/detail?JGLOBAL_ID=201702232979851703",
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"Physics",
"Ignition system",
"Atomic physics",
"Nuclear physics",
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"Hot spot (veterinary medicine)",
"National Ignition Facility",
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"abstract": "We have remotely monitored the thermodynamic phase of deuteriumtritium DT fuel inside glass shells used for inertial confinement fusion ICF research by observing the xray emissions from the shell. These studies are an adjunct to our beta heating experimental program.. By monitoring the production of lowenergy rays 18.6 keV from the interaction of the beta decay with the shell walls, we are able to track phase changes between gas and solid. We incorporated the mature xray detection technology of scintillators and photomultiplier tubes onto the experimental apparatus we use to study the beta heating effect.. Restrictive space limitations were a major hardware consideration in the retrofit. We review the scientific basis for the technique, the proof of principle experiment that encouraged us to pursue it, and the final experimental...",
"title": "Study of x-ray emissions from cold deuterium-tritium fuel inside glass targets for inertial confinement fusion",
"URL": "http://ui.adsabs.harvard.edu/abs/1990JVSTA...8.1745M/abstract",
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"Photomultiplier",
"Physics",
"Scintillator",
"Atomic physics",
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"Shell (structure)",
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"abstract": "A pseudoline source is realized by using an accelerator-based deuterium-tritium point-neutron source. The pseudoline source is obtained by time averaging of the continuously moving point source or by superposition of the finely distributed point sources. The line source is utilized for fusion blanket neutronics experiments with an annular geometry to simulate a part of a tokamak reactor. The source neutron characteristics are measured for two operational modes for the line source the continuous and the stepwise modes, with activation foil and NE-213 detectors, respectively. The neutron source characteristic is calculated by a Monte Carlo code to give a source condition for a successive calculational analysis of the annular blanket experiment. The reliability of the Monte Carlo calculation is confirmed by comparison with the measured source characteristics. 18 refs., 19 figs., 2 tabs.",
"title": "Concept and Characteristics of a Simulated Line Source for Annular Blanket Experiments Using an Accelerator-Based Deuterium-Tritium Neutron Source",
"URL": "https://experts.umn.edu/en/publications/concept-and-characteristics-of-a-simulated-line-source-for-annula",
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"abstract": "This paper reconsiders the magneto-inertia confinement approach to fusion in dynamic -pinch with a new method of generating a hot plasma using a frozen deuterium-tritium D-T tube as an initial condition. If modern pulsed power technology can induce the high current of the order of 10 MA along the tube, the dense -pinch plasma formed from the electro-magnetical implosion of thin tubular D-T ice with a radius of about 1 mm can satisfy the Lawson criterion for its 1 cm length.",
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"abstract": "Inertial confinement fusion ICF is one of the possible ways to realize controlled thermonuclear fusion. The fusion neutron source term is one of the important parameters in the physical design and analysis of laser plasma. The accuracy of the fusion neutron source term directly affects the reliability of the analysis results. At present, the neutron source term of deuterium-tritium fusion reaction in ICF is mainly based on formula method. It has limited applications in temperature and reaction type. Because of a large quantity of data, it is impossible to simulate the fusion reaction of each particle. In this paper, the concept of particle cloud is introduced, that is, the collection of the like particles with the same position and speed, and it is considered that the action of particle cloud is the same reaction. Because the particles should satisfy the Maxwell velocity distribution at a certain temperature and the direction is all around the circumference angle, the collision cross sections between the incident particle and different target particles are different. Therefore, the design program takes all the possible velocities, polar angles and direction angles, reads the collision cross sections between deuterium and tritium and makes corrections, and obtains the multi-temperature differential correction cross sections of deuterium and tritium fusion with Doppler energy broadening. On these bases, Monte Carlo method and discrete ordinate method method are used. A numerical simulation program for the fusion rate of D-T particles in laser plasma is developed in this paper. It is found that there are significant differences between the DT, DD, TD cross sections and the original cross sections after Doppler broadening. In a range of plasma temperature between 20 keV and 100 keV, the simulation results are more consistent with the cross section data of ENDFB-VI and ENDFB-VII databases of deuterium-tritium fusion reaction than those from the analytical formula method. There is a large error between the numerical simulation results and the analytical formula method in the low energy region. It may be caused by the difference of calculation methods and too big difference among the used fusion cross sections at low temperature.",
"title": "Numerical simulation of deuterium-tritium fusion reaction rate in laser plasma based on Monte Carlo-discrete ordinate method",
"URL": "http://dx.doi.org/10.7498/aps.68.20190440",
"fields_of_study": [
"Ordinate",
"Materials science",
"Monte Carlo method",
"Computational physics",
"Computer simulation",
"Laser",
"Deuterium",
"Tritium",
"Nuclear fusion",
"Plasma"
],
"year_published": 2019,
"first_author": "Zhong Chen",
"scholarly_citations_count": 2,
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"sentence": "A numerical simulation program for the fusion rate of D-T particles in laser plasma is developed in this paper.",
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"sentence": "It is found that there are significant differences between the DT, DD, TD cross sections and the original cross sections after Doppler broadening.",
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"sentence": "In a range of plasma temperature between 20 keV and 100 keV, the simulation results are more consistent with the cross section data of ENDFB-VI and ENDFB-VII databases of deuterium-tritium fusion reaction than those from the analytical formula method.",
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{
"abstract": "A projectile penetrates with high velocity the lid of a gas receptacle, compresses and heats a statically precompressed volume of a gaseous deuterium-tritium mixture, and may possibly start fusion...",
"title": "Compression and Heating of a Gaseous Deuterium-Tritium Mixture by Means of Cascaded Light Gas Guns and Its Possible Application to Nuclear Fusion",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/NSE04-A2436",
"fields_of_study": [
"Nuclear engineering",
"Fusion",
"Nuclear physics",
"Materials science",
"Volume (thermodynamics)",
"Projectile",
"Nuclear reactor",
"Deuterium",
"Tritium",
"Nuclear fusion",
"Shock wave"
],
"year_published": 2004,
"first_author": "D. Hofmann",
"scholarly_citations_count": "NaN",
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{
"abstract": "Abstract A single-crystal diamond detector is fabricated to diagnose 14.1 MeV deuteriumtritium D-T fusion neutrons. The size of its diamond film is 4.5 mm 4.5 mm 500 μm. This film is sandwiched by a flat, strip-patterned gold electrode. The dark current of this detector is experimentally measured to be lower than 0.1 nA under an electric field of 30 kV cm1. This diamond detector is used to measure D-T fusion neutrons with a flux of about 7.5 105 s1 cm2. The pronounced peak with a central energy of 8.28 MeV characterizing the C 12 , α B 9 reaction in the neutron energy spectrum is experimentally diagnosed, and the energy resolution is better than 1.69, which is the best result reported so far using a diamond detector. A clear peak with a central energy of 6.52 MeV characterizing the C 12 , 3 α reaction is also identified with an energy resolution of better than 7.67.",
"title": "Fabrication of a single-crystal diamond neutron detector and its application in 14.1 MeV neutron detection in deuterium–tritium fusion experiments",
"URL": "NaN",
"fields_of_study": [
"Analytical Chemistry (journal)",
"Materials science",
"Neutron generator",
"Diamond",
"Neutron",
"Physics",
"Chemistry",
"Neutron temperature",
"Nuclear physics",
"Chromatography",
"Composite material"
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"year_published": 2023,
"first_author": "Ping XU",
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{
"abstract": "Radiation-driven, layered deuterium-tritium plastic capsule implosions were carried out using a new, 3-shock adiabat-shaped drive on the National Ignition Facility. The purpose of adiabat shaping is to use a stronger first shock, reducing hydrodynamic instability growth in the ablator. The shock can decay before reaching the deuterium-tritium fuel leaving it on a low adiabat and allowing higher fuel compression. The fuel areal density was improved by 25 with this new drive compared to similar high-foot implosions, while neutron yield was improved by more than 4 times, compared to low-foot implosions driven at the same compression and implosion velocity.",
"title": "First results of radiation-driven, layered deuterium-tritium implosions with a 3-shock adiabat-shaped drive at the National Ignition Facility",
"URL": "https://inis.iaea.org/search/search.aspx?orig_q=RN:47060091",
"fields_of_study": [
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"Nuclear engineering",
"Physics",
"Neutron",
"Radiation",
"Nuclear physics",
"Area density",
"Implosion",
"National Ignition Facility",
"Fluid mechanics",
"Shock (mechanics)"
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"first_author": "V. A. Smalyuk",
"scholarly_citations_count": 30,
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"abstract": "A high-resolution optical imaging system and custom-designed image analysis software are used to make surface roughness measurements for deuterium-tritium D-T solid layers, equilibrated inside a...",
"title": "High-Resolution Optical Measurements of Surface Roughness for Beta-Layered Deuterium-Tritium Solid Inside a Re-Entrant Copper Cylinder",
"URL": "http://www.osti.gov/scitech/biblio/380828-high-resolution-optical-measurements-surface-roughness-beta-layered-deuterium-tritium-solid-inside-re-entrant-copper-cylinder",
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"Inertial confinement fusion",
"Optics",
"Materials science",
"Instrumentation",
"Surface finishing",
"Beta (plasma physics)",
"Deuterium",
"Tritium",
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"year_published": 1996,
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"abstract": "This paper reports first observations in a tokamak plasma of MeV energy ions produced by close elastic collisions knock-on between deuteriumtritium fusion α-particles and thermal plasma fuel ions. Measurements of flux of MeV energy helium and deuterium atoms from the plasma in the Joint European Torus were made from which line-integrated energy distribution function of knock-on deuterons, FdE, was deduced. Neutralization of the deuterons and α-particles was effected by charge-exchange with one- and two-electron species of the main intrinsic plasma impurities, carbon, beryllium, and helium. Deduced FdE is shown to be in agreement with calculations using classical confinement and slowing-down of fusion α-particles and knock-on deuterons.",
"title": "Observation of MeV energy deuterons produced by knock-on collisions between deuterium–tritium fusion α-particles and plasma fuel ions",
"URL": "https://ui.adsabs.harvard.edu/abs/2000PhPl....7..957K/abstract",
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"Physics",
"Magnetic confinement fusion",
"Lawson criterion",
"Atomic physics",
"Nuclear physics",
"Fusion power",
"Joint European Torus",
"Dense plasma focus",
"Thermonuclear fusion",
"Plasma"
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"first_author": "A. A. Korotkov",
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{
"abstract": "Electron-temperature Te measurements in implosions provide valuable diagnostic information, as Te is unaffected by residual flows and other non-thermal effects unlike ion temperature inferred from a fusion product spectrum. In OMEGA cryogenic implosions, measurement of Tet can be used to investigate effects related to time-resolved hot-spot energy balance. The proposed diagnostic utilizes five fast-rise 15 ps scintillator channels with distinct -ray filtering. Titanium and stepped aluminum filtering were chosen to maximize detector sensitivity in the 10 keV-20 keV range, as it has been shown that these rays have similar density and temperature weighting to the emitted deuterium-tritium fusion neutrons. Initial data collected using a prototype nosecone on the existing neutron temporal diagnostic demonstrate the validity of this diagnostic technique. The proposed system will be capable of measuring spatially integrated Tet with 20 ps time resolution and 10 uncertainty at peak emission in cryogenic DT implosions.",
"title": "A multi-channel x-ray temporal diagnostic for measurement of time-resolved electron temperature in cryogenic deuterium-tritium implosions at OMEGA.",
"URL": "http://ui.adsabs.harvard.edu/abs/2021RScI...92b3507K/abstract",
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"Neutron",
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"X-ray",
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"Deuterium",
"Detector"
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"year_published": 2021,
"first_author": "Neel Kabadi",
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"abstract": "A three-dimensional model of the hot-spot -ray emission has been developed and applied to the study of low-mode drive asymmetries in direct-drive inertial confinement fusion implosions on OMEGA with cryogenic deuterium-tritium targets. The steady-state model assumes an optically thin plasma and the data from four -ray diagnostics along quasi-orthogonal lines of sight are used to obtain a tomographic reconstruction of the hot spot. A quantitative analysis of the hot-spot shape is achieved by projecting the -ray emission into the diagnostic planes and comparing this projection to the measurements. The model was validated with radiation-hydrodynamic simulations assuming a mode-2 laser illumination perturbation resulting in an elliptically shaped hot spot, which was accurately reconstructed by the model using synthetic -ray images. This technique was applied to experimental data from implosions in polar-direct-drive illumination geometry with a deliberate laser-drive asymmetry, and the hot-spot emission was reconstructed using spherical-harmonic modes of up to ℓ 3. A 10 stronger drive on the equator relative to that on the poles resulted in a prolate-shaped hot spot at stagnation with a large negative A2,0 coefficient of A2,0-0.47 0.03, directly connecting the modal contribution of the hot-spot shape with the modal contribution in laser-drive asymmetry.",
"title": "Three-dimensional hot-spot x-ray emission tomography from cryogenic deuterium-tritium direct-drive implosions on OMEGA.",
"URL": "https://aip.scitation.org/doi/10.1063/5.0098977",
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"abstract": "Measurements and preliminary analysis have been completed on limiter heating during high fusion power deuteriumtritium DT operation of the Tokamak Fusion Test Reactor TFTR in an attempt to identify heating from first orbit and ripple losses of fast alpha particles. Recent operation of TFTR with a 5050 mix of DT has resulted in fusion power output 6.2 MW orders of magnitude above what was previously achieved on TFTR. A significantly larger absolute number of particles and energy from fusion products, compared to DD operation, are expected to be lost to the limiters. Power and energy estimates of total alpha losses were as high as 0.13 MW and 64 kJ. Measurements were made in the vicinity of the outer midplane, where most of the losses are expected, with thermocouples mounted on the tiles of a limiter. With an increasingly more reactive mixture of D and T at constant beam power, there was a measurable increase in the limiter tile temperature as the fusion power and alpha yield increased. The meas...",
"title": "Measurement of limiter heating due to alpha particle losses during high fusion power deuterium‐tritium operation of the TFTR tokamak",
"URL": "http://www.osti.gov/scitech/biblio/6709425-measurement-limiter-heating-due-alpha-particle-losses-during-high-fusion-power-deuterium-tritium-operation-tftr-tokamak",
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"abstract": "For the first time high areal-density ρR cryogenic deuterium-tritium DT implosions have been probed using downscattered neutron spectra measured with the magnetic recoil spectrometer MRS, recently installed and commissioned on OMEGA. The ρR data obtained with the MRS have been essential for understanding how the fuel is assembled and for guiding the cryogenic program at the Laboratory for Laser Energetics LLE to ρR values up to 300 mgcm2. The ρR data obtained from well-established charged particle spectrometry techniques were used to authenticate the MRS data for low-ρR plastic capsule implosions, and the ρR values inferred from these techniques are in excellent agreement, indicating that the MRS technique provides high-fidelity data. Recent OMEGA-MRS data and Monte Carlo simulations have shown that the MRS on the NIF G. H. Miller et al....",
"title": "Probing high areal-density cryogenic deuterium-tritium implosions using downscattered neutron spectra measured by the magnetic recoil spectrometera)",
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"abstract": "Areal density is one of the key parameters that determines the confinement time in inertial confinement fusion experiments, and low-mode asymmetries in the compressed fuel are detrimental to the implosion performance. The energy spectra from the scattering of the primary deuterium-tritium DT neutrons off the compressed cold fuel assembly are used to investigate low-mode nonuniformities in direct-drive cryogenic DT implosions at the Omega Laser Facility. For spherically symmetric implosions, the shape of the energy spectrum is primarily determined by the elastic and inelastic scattering cross sections for both neutron-deuterium and neutron-tritium kinematic interactions. Two highly collimated lines of sight, which are positioned at nearly orthogonal locations around the OMEGA target chamber, record the neutron time-of-flight signal in the current mode. An evolutionary algorithm is being used to extract a model-independent energy spectrum of the scattered neutrons from the experimental neutron time-of-flight data and is used to infer the modal spatial variations 1 in the areal density. Experimental observations of the low-mode variations of the cold-fuel assembly ρL0 ρL1 show good agreement with a recently developed model, indicating a departure from the spherical symmetry of the compressed DT fuel assembly. Another key signature that has been observed in the presence of a low-mode variation is the broadening of the kinematic end-point due to the anisotropy of the dense fuel conditions.",
"title": "Measurements of low-mode asymmetries in the areal density of laser-direct-drive deuterium-tritium cryogenic implosions on OMEGA using neutron spectroscopy.",
"URL": "http://spiral.imperial.ac.uk/bitstream/10044/1/100465/5/5.0101812.pdf",
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"Inertial confinement fusion",
"Nuclear physics",
"Neutron spectroscopy",
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"abstract": "Using first-principles FP methods, we have performed ab initio compute for the equation of state EOS, thermal conductivity, and opacity of deuterium-tritium DT in a wide range of densities and temperatures for inertial confinement fusion ICF applications. These systematic investigations have recently been expanded to accurately compute the plasma properties of CH ablators under extreme conditions. In particular, the first-principles EOS and thermal-conductivity tables of CH are self-consistently built from such FP calculations, which are benchmarked by experimental measurements. When compared with the traditional models used for these plasma properties in hydrocodes, significant differences have been identified in the warm dense plasma regime. When these FP-calculated properties of DT and CH were used in our hydrodynamic simulations of ICF implosions, we found that the target performance in terms of neutron yield and energy gain can vary by a factor of 2 to 3, relative to traditional model simulations.",
"title": "First-principles studies on the equation of state, thermal conductivity, and opacity of deuterium-tritium (DT) and polystyrene (CH) for inertial confinement fusion applications",
"URL": "https://iopscience.iop.org/article/10.1088/1742-6596/717/1/012064",
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"Atomic physics",
"Chemistry",
"Range (particle radiation)",
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"Deuterium",
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"Plasma",
"Thermal conductivity"
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"year_published": 2016,
"first_author": "Suxing Hu",
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"abstract": "Electron-impact total and dissociative cross sections, calculated by using the impact-parameter method, for the X1Σg B1Σu and X1Σg C1Πu transitions of vibrationally excited T2 and DT molecules, are presented. The mass and vibrational energy scalings of these cross sections are discussed.",
"title": "Total and Dissociative Electron-impact Cross Sections for X1Σg+ → B1Σu+ and X1Σg+ → C1Πu Transitions of Vibrationally Excited Tritium and Deuterium-Tritium Molecules",
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"abstract": "We measured the equilibrium constants KHDO P2HDOPH2OPD2O, KHTO P2HTOPH2OPT2O, and KDTO P2DTOPD2OPT2O at 295.6K 22.4C, assuming the mass spectrometric sensitivities of the three species cancel in each expression of the equilibrium constant. The results obtained were KHDO 3.820.05, KHTO 3.660.06, and KDTO 3.990.07. These values agreed with the current theoretical values of KHDO 3.84, KHTO 3.69, and KDTO 3.97 at the same temperature. We discuss the discrepancy of the present value of KHDO as compared with previous experimental determinations, and we conclude that a direct measurement of the mass spectrometric sensitivity ratio for KHDO is still necessary to resolve the disagreement. We prepared the water mixtures that contained tritium by reacting the appropriate hydrogenic gases with oxygen over a platinum sponge catalyst.",
"title": "Equilibrium constants of hydrogen–deuterium–tritium self‐exchange reactions in water vapor as studied with a pulsed molecular‐beam quadrupole mass filter",
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"abstract": "Volume ignition, in which fuel is usually surrounded by pushers made from high-Z materials, is an approach to inertial confinement fusion. High-Z pushers have high albedos, which means that they can re-radiate most of the radiation coming from the hot fuel. Hence, it is beneficial to realize ignition at lower temperatures. We develop a theoretical model comprising a set of coupled equations to model the radiation heat conduction between the hot fuel and the high-Z pusher. We then investigate the dependence of the albedo of the high-Z pusher on the state of the hot fuel. The results of our model show good consistency with numerical simulations. Furthermore, the physics of the radiation heat conduction between the hot fuel and the high-Z pusher in volume ignition is elucidated, which is important for follow-up studies of the critical values for volume ignition and for obtaining a physical picture of fusion burning. The model can also provide some theoretical basis for the design of double-shell targets and energy targets.",
"title": "A theoretical model for radiation heat conduction between deuterium–tritium fuel and a high-Z pusher in volume ignition in inertial confinement fusion",
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"abstract": "Based on our previous work Phys. Plasmas 25 012704 2018, a fitting formula is given for electronion energy partition fraction of 3.54-MeV fusion alpha particles in deuteriumtritium DT plasmas as a function of plasma mass density ρ, electron temperature T , and ion temperature T . The formula can be used in a huge range of the plasma state, where ρ varies between 1.0 gcc 10.03 gcc and both T and T change from 0.1 keV to 100.0 keV. Relativistic effect for electrons is investigated including the effect of the projectile recoil in the plasmas at T 50.0 keV. The partition fraction for T gt T is found to be close to that for T T . The comparisons with other fitting results are made at some plasma densities when T T , and the difference is explained. The fitting result is very close to the calculated one in most cases, which is convenient for the simulation of alpha heating in hot dense DT plasmas for inertial confined fusion.",
"title": "A fitting formula for electron-ion energy partition fraction of 3.54-MeV fusion alpha particles in hot dense deuterium-tritium plasmas",
"URL": "http://ui.adsabs.harvard.edu/abs/2021ChPhB..30a5202Z/abstract",
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"Materials science",
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"abstract": "A fusion reactor requires plasma pre-heating before the rate of deuterium-tritium fusion reactions becomes significant. In ITER, radio frequency RF heating of 3He ions, additionally puffed into the plasma, is one of the main options considered for increasing bulk ion temperature during the ramp-up phase of the pulse. In this paper, we propose an alternative scenario for bulk ion heating with RF waves, which requires no extra 3He puff and profits from the presence of intrinsic Beryllium impurities in the plasma. The discussed method to heat Be impurities in D-T plasmas is shown to provide an even larger fraction of fuel ion heating.",
"title": "A new ion cyclotron range of frequency scenario for bulk ion heating in deuterium-tritium plasmas: How to utilize intrinsic impurities in our favour",
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"abstract": "Production of, and nuclei in central interactions was studied at five collision energies, 7.6, 8.8, 12.3, and 17.3 GeV with the NA49 detector at the CERN Super Proton Synchrotron. Transverse momentum spectra, rapidity distributions, and particle ratios were measured. Yields are compared to predictions of statistical models. Phase-space distributions of light nuclei are discussed and compared to those of protons in the context of a coalescence approach. The coalescence parameters and, as well as coalescence radii for and were determined as a function of transverse mass at all energies.",
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"abstract": "Intense fluxes of 14MeV neutrons from deuteriumtritium DT fusion reaction in TFTR resulted in significantly enhanced background noise levels and reduced quality of data from the shielded UV SPRED and visible VIPS grating spectrometers and the xray imaging system XIS camera. Both enhanced background levels, attributed to gamma rays and small angle neutron scattering, and large spikes, attributed to nuclear reactions in the silicon detectors, were observed. Both the enhanced background and the frequency of spikes were higher, on a per neutron basis, and the spike amplitudes were higher for DT than for DD operation. The VIPS shield reduced noise by 1100 for DD radiation the noise per DT neutron was 4 times higher than per DD neutron. The SPRED detector shield reduction factor was 112 in DD extension of the shield around the vacuum chamber resulted in another factor of 15.5 reduction for DT plasmas. Spikes with amplitude up to 10 MeV were observed in the XIS detectors. The shielding effectiveness agrees with predictions. The spike heights are consistent with , and ,α reactions in the silicon detectors.",
"title": "Analysis of nuclear‐radiation‐induced noise in spectroscopic and x‐ray diagnostics during high power deuterium–tritium experiments on the tokamak fusion test reactor",
"URL": "https://aip.scitation.org/doi/10.1063/1.1146203",
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"Physics",
"Neutron",
"Radiation",
"Noise (radio)",
"Nuclear physics",
"Nuclear reaction",
"Tokamak Fusion Test Reactor",
"Nuclear fusion",
"Gamma ray",
"Neutron flux"
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"year_published": 1995,
"first_author": "K. W. Hill",
"scholarly_citations_count": 7,
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"abstract": "The Joint European Torus JET is playing an important role in preparing for the operation of the future worlds largest tokomak, ITER. In this respect, the tritium campaign C40 and second deuteriumtritium experiment DTE2, C41 took place in the JET during the years 2021 and 2022. In this work, a corresponding irradiation scenario was utilized for the activation calculations of eight material foils located at the JET outer long-term irradiation station OLTIS. Neutron-induced activities and dose rates at a 30 cm distance after shutdown at specified cooling intervals were calculated with the FISPACT-II code, employing the EAF-2010 nuclear and TENDL-2021 data libraries. The Monte Carlo MCNP6.2 particle transport code equipped with the FENDL-3.1d nuclear data library was used for the calculation of the neutron flux densities.",
"title": "Activity and Dose Rate Calculations for Joint European Torus Outer Long-Term Irradiation Station during Tritium and Second Deuterium Tritium Experiment Campaigns",
"URL": "https://www.mdpi.com/2076-3417/14/7/2674/pdf?version=1711094706",
"fields_of_study": [
"Tritium",
"Nuclear physics",
"Deuterium",
"Radiochemistry",
"Dose rate",
"Term (time)",
"Joint European Torus",
"Environmental science",
"Physics",
"Chemistry",
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"year_published": 2024,
"first_author": "Andrius Tidikas",
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"abstract": "The values of the externally applied thermal gradients that give rise to uniform liquid layers of a ternary deuteriumtritium mixture inside a cryogenic spherical shell inertial confinement fusion target are calculated using a model recently developed by the authors. It is shown that the surface tension gradients induced by the component separation at the liquidvapor interface pull the liquid upward, thus counteracting the gravityinduced fuel sagging and forming dynamically stable uniform liquid layers. The governing equations are the equations of continuity, momentum, energy, and mass diffusionconvection, which are solved using finitedifference methods. The solutions indicate that one needs fairly large positive thermal gradients, obtained by keeping the top of the target warmer than the bottom, in order to create uniform liquid layers on the inner surface of the target.",
"title": "An analysis of the thermally induced formation of a uniform liquid layer of ternary deuterium–tritium mixture inside a cryogenic spherical shell inertial confinement fusion target",
"URL": "http://ui.adsabs.harvard.edu/abs/1988JVST....6.1876V/abstract",
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"Inertial confinement fusion",
"Spherical shell",
"Fabrication",
"Atomic physics",
"Chemistry",
"Thermal",
"Mechanics",
"Momentum",
"Deuterium",
"Ternary operation",
"Surface tension"
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"year_published": 1988,
"first_author": "V. Varadarajan",
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"abstract": "The recently proposed super-Marx generator pure deuterium microdetonation ignition concept is compared to the Lawrence Livermore National Ignition Facility NIF Laser deuterium-tritium fusion-fission hybrid concept LIFE. In a super-Marx generator, a large number of ordinary Marx generators charge up a much larger second stage ultrahigh voltage Marx generator from which for the ignition of a pure deuterium microexplosion an intense GeV ion beam can be extracted. Typical examples of the LIFE concept are a fusion gain of 30 and a fission gain of 10, making up a total gain of 300, with about ten times more energy released into fission as compared to fusion. This means the substantial release of fission products, as in fissionless pure fission reactors. In the super-Marx approach for the ignition of pure deuterium microdetonation, a gain of the same magnitude can, in theory, be reached. If feasible, the super-Marx generator deuterium ignition approach would make lasers obsolete as a means for the ignition of thermonuclear microexplosions.",
"title": "Comparison of the recently proposed super-Marx generator approach to thermonuclear ignition with the deuterium-tritium laser fusion-fission hybrid concept by the Lawrence Livermore National Laboratory",
"URL": "https://aip.scitation.org/doi/10.1063/1.3253693",
"fields_of_study": [
"Fission products",
"Inertial confinement fusion",
"Marx generator",
"Fission",
"Nova (laser)",
"Ignition system",
"Nuclear physics",
"Chemistry",
"National Ignition Facility",
"Thermonuclear fusion"
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"year_published": 2009,
"first_author": "Friedwardt Winterberg",
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"abstract": "Millimeter-sized CD foils fielded close order mm to inertial confinement fusion ICF implosions have been proposed as a game-changer for improving energy resolution and allowing time-resolution in neutron spectrum measurements using the magnetic recoil technique. This paper presents results from initial experiments testing this concept for direct drive ICF at the OMEGA Laser Facility. While the foils are shown to produce reasonable signals, inferred spectral broadening is seen to be high 5 keV and signal levels are low by 20 compared to expectation. Before this type of foil is used for precision experiments, the foil mount must be improved, oxygen uptake in the foils must be better characterized, and impact of uncontrolled foil motion prior to detection must be investigated.",
"title": "Using millimeter-sized carbon-deuterium foils for high-precision deuterium-tritium neutron spectrum measurements in direct-drive inertial confinement fusion at the OMEGA laser facility.",
"URL": "https://aip.scitation.org/doi/10.1063/5.0040549",
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"Millimeter",
"Optics",
"Neutron",
"Materials science",
"Recoil",
"Laser",
"Deuterium",
"Doppler broadening",
"FOIL method"
],
"year_published": 2021,
"first_author": "M. Gatu Johnson",
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"abstract": "One- and two-dimensional multigroup radiation hydrodynamics simulations have been performed to investigate the motion of the gold plasma generated at the surface of the embedded gold cone in a re-entrant cone-guided inertial confinement fusion capsule. The effect of deuterium-tritium DT ice layers, and other possible tampers, of varying thickness, upon the motion of the gold cone plasma has been investigated. The effect of the -ray drive spectrum incident upon the ice layer is also explored. Ice is shown to tamp the expansion of the gold cone, and whilst denser materials are shown to be more effective in this role, ice does not pollute the ignition region with intermediate-Z ions, which, though preferable to gold contamination, also tend to inhibit the attainment of high fuel-ion temperatures.",
"title": "Simulations investigating the effect of a deuterium-tritium-ice coating on the motion of the gold cone surface in a re-entrant cone-guided fast ignition inertial confinement fusion capsule",
"URL": "https://aip.scitation.org/doi/10.1063/1.2734584",
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"Physics",
"Ion",
"Ignition system",
"Atomic physics",
"Layer (electronics)",
"Coating",
"Laser",
"Mechanics",
"Deuterium",
"Plasma"
],
"year_published": 2007,
"first_author": "John Pasley",
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{
"abstract": "Low- and mid-mode perturbations are possible candidates for performance limitations in cryogenic direct-drive implosions on the OMEGA laser at the Laboratory of Laser Energetics. Simulations with a 3D hydrocode demonstrated that hotspot imagers do not show evidence of the shell breakup in the dense fuel. However, these same simulations revealed that the low- and mid-mode perturbations in the dense fuel could be diagnosed more easily in the post-stagnation phase of the implosion by analyzing the peak in the -ray emission limb at the coronal-fuel interface than before or at the stagnation phase. In experiments, the asymmetries are inferred from gated images of the -ray emission of the implosion by using a 16-pinhole array imager filtered to record -ray energies 800 eV and an -ray framing camera with 40-ps time integration and 20-μm spatial resolution. A modal analysis is applied to the spatial distribution of the -ray emission from deuterium and tritium cryogenic implosions on OMEGA recorded after the bang time to diagnose the low- and mid-mode asymmetries, and to study the effect that the beam-to-target ratio RbRt has on the shell integrity.",
"title": "Diagnosing low-mode (ℓ < 6) and mid-mode (6 ≤ ℓ ≤ 60) asymmetries in the post-stagnation phase of laser-direct-drive deuterium-tritium cryogenic implosions on OMEGA.",
"URL": "https://aip.scitation.org/doi/10.1063/5.0101653",
"fields_of_study": [
"Implosion",
"Hohlraum",
"Plasma diagnostics",
"Physics",
"Laser",
"Optics",
"Deuterium",
"Plasma",
"Inertial confinement fusion",
"Atomic physics",
"Nuclear physics",
"Materials science"
],
"year_published": 2022,
"first_author": "J Baltazar",
"scholarly_citations_count": 1,
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"sentence": "However, these same simulations revealed that the low- and mid-mode perturbations in the dense fuel could be diagnosed more easily in the post-stagnation phase of the implosion by analyzing the peak in the -ray emission limb at the coronal-fuel interface than before or at the stagnation phase.",
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"entity": "stagnation phase"
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"sentence": "A modal analysis is applied to the spatial distribution of the -ray emission from deuterium and tritium cryogenic implosions on OMEGA recorded after the bang time to diagnose the low- and mid-mode asymmetries, and to study the effect that the beam-to-target ratio RbRt has on the shell integrity.",
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"category": "Nuclear Fusion Experimental Facility",
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"entity": "Tritium"
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"category": "Nuclear Fusion System Component",
"entity": "Shell"
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{
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"entity": "Target"
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"abstract": "Benchmark experiments for the validation of secondary-gamma-ray data are conducted for iron and Type 316 stainless steel SS316 shield assemblies bombarded by deuterium-tritium neutrons. Gamma-ray spectra and heating rates for both threshold and capture gamma rays are measured. With the present experimental data for gamma rays, a set of benchmark data for iron and SS316, including neutron energy spectra in entire energies and various dosimetry reaction rates, is completed for the first time. Secondary-gamma-ray data in JENDL-3.1, JENDL-3.2, JENDL-Fusion File, and FENDL E-1. 0 are tested by benchmark calculation of the experiments. As a result, larger gamma-ray-production cross sections for threshold reactions in JENDL-3. and JENDL-3.2 and an inconsistent energy balance of the ,γ reactions in JENDL-3.1 are found. From the viewpoint of fusion engineering, the first priority in evaluating secondary-gamma-ray data should be conserving the energy balance. A rigid energy balance in both the JENDL Fusion File and FENDLE-1.0 is confirmed for both threshold and capture gamma rays. The JENDL Fusion File and FENDLE-1.0 provide the highly accurate secondary-gamma-ray data for iron and SS316 needed for fusion reactor nuclear design.",
"title": "Measurement of Gamma-Ray Spectra and Heating Rates in Iron and Stainless Steel Shields Bombarded by Deuterium-Tritium Neutrons and Validation of Secondary-Gamma-Ray Data in Evaluated Nuclear Data Libraries",
"URL": "https://www.ans.org/pubs/journals/nse/a_24472",
"fields_of_study": [
"Shields",
"Neutron",
"Nuclear physics",
"Materials science",
"Fusion power",
"Neutron temperature",
"Nuclear data",
"Deuterium",
"Tritium",
"Gamma ray"
],
"year_published": 1997,
"first_author": "Fujio Maekawa",
"scholarly_citations_count": 5,
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"entity": "Iron"
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"sentence": "With the present experimental data for gamma rays, a set of benchmark data for iron and SS316, including neutron energy spectra in entire energies and various dosimetry reaction rates, is completed for the first time.",
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"sentence": "Secondary-gamma-ray data in JENDL-3.1, JENDL-3.2, JENDL-Fusion File, and FENDL E-1.",
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"entity": "JENDL-3.1"
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"sentence": "0 are tested by benchmark calculation of the experiments.",
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"entity": "benchmark calculation"
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"sentence": "As a result, larger gamma-ray-production cross sections for threshold reactions in JENDL-3.",
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"category": "Database",
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"sentence": "A rigid energy balance in both the JENDL Fusion File and FENDLE-1.0 is confirmed for both threshold and capture gamma rays.",
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"category": "Database",
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"entity": "capture gamma rays"
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{
"category": "Physical Process",
"entity": "threshold gamma rays"
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]
},
{
"sentence": "The JENDL Fusion File and FENDLE-1.0 provide the highly accurate secondary-gamma-ray data for iron and SS316 needed for fusion reactor nuclear design.",
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{
"category": "Database",
"entity": "JENDL Fusion File"
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"category": "Chemical Element or Compound",
"entity": "Iron"
},
{
"category": "Chemical Element or Compound",
"entity": "SS316"
},
{
"category": "Nuclear Fusion System Component",
"entity": "Fusion reactor"
}
]
}
]
},
{
"abstract": "This corrects the article DOI 10.1103PhysRevLett.117.025001.",
"title": "Publisher's Note: Demonstration of Fuel Hot-Spot Pressure in Excess of 50 Gbar for Direct-Drive, Layered Deuterium-Tritium Implosions on OMEGA [Phys. Rev. Lett. 117, 025001 (2016)].",
"URL": "https://www.ncbi.nlm.nih.gov/pubmed/27517797",
"fields_of_study": [
"Physics",
"Nuclear physics",
"Hot spot (veterinary medicine)",
"Omega",
"Deuterium",
"Tritium",
"Thermodynamics"
],
"year_published": 2016,
"first_author": "Susan Regan",
"scholarly_citations_count": 23,
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"sentence": "This corrects the article DOI 10.1103PhysRevLett.117.025001.",
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}
]
},
{
"abstract": "Neutron spectra below 10 keV in an iron shield assembly bombarded by deuterium-tritium neutrons are measured with accuracy between 5 to 13 by adopting the slowing-down time method. The measurement...",
"title": "Measurement of Neutron Energy Spectrum below 10 keV in an Iron Shield Bombarded by Deuterium-Tritium Neutrons and Benchmark Test of Evaluated Nuclear Data from 14 MeV to 1 eV",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/NSE97-A24267",
"fields_of_study": [
"Shield",
"Neutron",
"Nuclear physics",
"Materials science",
"Nuclear reaction",
"Electromagnetic shielding",
"Fusion power",
"Nuclear data",
"Deuterium",
"Tritium"
],
"year_published": 1997,
"first_author": "Fujio Maekawa",
"scholarly_citations_count": 8,
"NER-RE": [
{
"sentence": "Neutron spectra below 10 keV in an iron shield assembly bombarded by deuterium-tritium neutrons are measured with accuracy between 5 to 13 by adopting the slowing-down time method.",
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"category": "Particle",
"entity": "neutron"
},
{
"category": "Particle",
"entity": "deuterium-tritium neutrons"
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"entity": "iron"
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"entity": "iron"
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"category": "Nuclear Fusion Technique",
"entity": "slowing-down time method"
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{
"category": "Experimental Apparatus",
"entity": "iron shield assembly"
},
{
"category": "Detection and Monitoring Systems",
"entity": "neutron spectra"
}
]
}
]
},
{
"abstract": "Accurate quantum total reaction probabilities for the collinear reaction X Fsub 2 upsilon 0.1..--.. XF F X Mu, H, D, T have been used to calculate collinear rate constants and activation energies. Comparison is made with collinear quasi-classical trajectory calculations and transition state theory assuming classical motion along a separable reaction coordinate and vibrational adiabaticity. Considerable differences between the quantum and quasi-classical and transition state theory results are found only for the Mu reaction at low temperatures. 5 figures, 35 references, 6 tables.",
"title": "Comparison of quasi-classical, transition state theory, and quantum calculations of rate constants and activation energies for the collinear reaction X + F2 .fwdarw. XF + F (X = muonium, hydrogen, deuterium, tritium)",
"URL": "https://pubs.acs.org/doi/pdf/10.1021/j100464a013",
"fields_of_study": [
"Quantum field theory",
"Atomic physics",
"Reaction coordinate",
"Chemistry",
"Muonium",
"Transition state theory",
"Deuterium",
"Kinetic isotope effect",
"Reaction rate constant",
"Activation energy"
],
"year_published": 1979,
"first_author": "J. N. L. Connor",
"scholarly_citations_count": 38,
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{
"sentence": "Accurate quantum total reaction probabilities for the collinear reaction X Fsub 2 upsilon 0.1..--..",
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"sentence": "XF F X Mu, H, D, T have been used to calculate collinear rate constants and activation energies.",
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"entity": "Mu"
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"entity": "D"
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{
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"category": "Theory and Calculation",
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{
"category": "Physical Process",
"entity": "classical motion along a separable reaction coordinate"
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"entity": "Mu"
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{
"abstract": "An effect of nuclear elastic scattering on the rate coefficient of fusion reaction between field deuteron and triton in the presence of neutral beam injection heating is studied. Without assuming a Maxwellian for bulk-ion distribution function, the Boltzmann-Fokker-Planck BFP equations for field bulk deuteron, field bulk triton, α-particle, and beam deuteron are simultaneously solved in an ITER-like deuterium-tritium thermonuclear plasma. The BFP calculation shows that enhancement of the reaction rate coefficient due to knock-on tail formation in fuel-ion distribution functions becomes appreciable, especially in the case of low-density operations.",
"title": "Distortion of bulk-ion distribution function due to nuclear elastic scattering and its effect on T(d,n)He4 reaction rate coefficient in neutral-beam-injected deuterium-tritium plasmas",
"URL": "https://kyushu-u.pure.elsevier.com/en/publications/distortion-of-bulk-ion-distribution-function-due-to-nuclear-elast",
"fields_of_study": [
"Physics",
"Reaction rate",
"Atomic physics",
"Distribution function",
"Elastic scattering",
"Fusion power",
"Neutral beam injection",
"Deuterium",
"Nuclear fusion",
"Thermonuclear fusion"
],
"year_published": 2007,
"first_author": "H. Matsuura",
"scholarly_citations_count": 12,
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"sentence": "An effect of nuclear elastic scattering on the rate coefficient of fusion reaction between field deuteron and triton in the presence of neutral beam injection heating is studied.",
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"entity": "deuteron"
},
{
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"entity": "triton"
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{
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"entity": "neutral beam injection heating"
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{
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"entity": "nuclear elastic scattering"
},
{
"category": "Physical Process",
"entity": "fusion reaction"
}
]
},
{
"sentence": "Without assuming a Maxwellian for bulk-ion distribution function, the Boltzmann-Fokker-Planck BFP equations for field bulk deuteron, field bulk triton, α-particle, and beam deuteron are simultaneously solved in an ITER-like deuterium-tritium thermonuclear plasma.",
"entities": [
{
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{
"abstract": "The authors measure crucial neutron cross sections for Xe, a fusion dopant in deuterium-tritium capsules, with a predicted high neutron-capture rate. The data provides an accurate experimental basis to interpret measurements of the XeXe ratio, which is a sensitive diagnostic tool for the fuel density of the plasma in the capsules during the implosion.",
"title": "Comprehensive sets of Xe 124 ( n , γ ) Xe 125 and Xe 124 ( n , 2 n ) Xe 123 cross-section data for assessment of inertial-confinement deuterium-tritium fusion plasma",
"URL": "http://www.osti.gov/pages/biblio/1181157-comprehensive-sets-xe-xe-xe-xe-cross-section-data-assessment-inertial-confinement-deuterium-tritium-fusion-plasma",
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Neutron",
"Atomic physics",
"Dopant",
"Implosion",
"Fusion plasma",
"Deuterium",
"Tritium",
"Plasma"
],
"year_published": 2015,
"first_author": "Megha Bhike",
"scholarly_citations_count": 16,
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"entity": "implosion"
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"entity": "Xe"
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"entity": "diagnostic tool"
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"entity": "XeXe ratio"
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]
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{
"abstract": "A 1000-MW electric fusion power reactor concept based on electrochemically induced D-Dsub eta, D-Dsub rho, and deuterium-tritium reactions is presented A D-sub 2sup 3He reaction is not possible because sub 2sup 3He is not absorbed in the electrode. The concept of a tube-type fuel cell is presented. The inner surface of the tube is laminated with palladium. The cell provides a large cathode surface and efficient heat transport to the water coolant. The fuel assemblies and bundles of fuel tubes are installed in the pressure vessel. The reactor system is very similar to a pressurized water reactor, through the reactor internals are much simplified due to the elimination of fission fuel pellets and control rods. The spatial power distribution of the reactor core is very flat compared with that of fission reactors.",
"title": "D/sub 2/O-fueled fusion power reactor using electrochemically induced D-D/sub n/, D-D/sub p/, and deuterium-tritium reactions; Preliminary design of a reactor system",
"URL": "https://ans.org/pubs/journals/fst/a_29160",
"fields_of_study": [
"Control rod",
"Nuclear engineering",
"Fission",
"Electrochemical cell",
"Materials science",
"Fusion power",
"Pressurized water reactor",
"Nuclear reactor core",
"Deuterium",
"Coolant"
],
"year_published": 1989,
"first_author": "Y. Oka",
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"sentence": "A 1000-MW electric fusion power reactor concept based on electrochemically induced D-Dsub eta, D-Dsub rho, and deuterium-tritium reactions is presented A D-sub 2sup 3He reaction is not possible because sub 2sup 3He is not absorbed in the electrode.",
"entities": [
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"category": "Concept",
"entity": "electric fusion power reactor"
},
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"category": "Nuclear Fusion Technique",
"entity": "electrochemically induced D-Dsub eta reaction"
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{
"category": "Nuclear Fusion Technique",
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{
"category": "Nuclear Fusion Technique",
"entity": "deuterium-tritium reaction"
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{
"category": "Particle",
"entity": "D"
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"category": "Particle",
"entity": "Dsub 2sup 3He"
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"category": "Particle",
"entity": "deuterium"
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{
"category": "Particle",
"entity": "tritium"
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"category": "Chemical Element or Compound",
"entity": "sub 2sup 3He"
},
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"category": "Nuclear Fusion System Component",
"entity": "electrode"
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]
},
{
"sentence": "The concept of a tube-type fuel cell is presented.",
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"category": "Concept",
"entity": "tube-type fuel cell"
}
]
},
{
"sentence": "The inner surface of the tube is laminated with palladium.",
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"category": "Chemical Element or Compound",
"entity": "palladium"
}
]
},
{
"sentence": "The cell provides a large cathode surface and efficient heat transport to the water coolant.",
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{
"category": "Nuclear Fusion System Component",
"entity": "cathode"
},
{
"category": "Experimental Apparatus",
"entity": "water coolant"
}
]
},
{
"sentence": "The fuel assemblies and bundles of fuel tubes are installed in the pressure vessel.",
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"category": "Nuclear Fusion System Component",
"entity": "fuel assemblies"
},
{
"category": "Nuclear Fusion System Component",
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"category": "Nuclear Fusion System Component",
"entity": "pressure vessel"
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]
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{
"sentence": "The reactor system is very similar to a pressurized water reactor, through the reactor internals are much simplified due to the elimination of fission fuel pellets and control rods.",
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"category": "Nuclear Fusion Device Type",
"entity": "pressurized water reactor"
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"category": "Nuclear Fusion System Component",
"entity": "fission fuel pellets"
},
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"category": "Nuclear Fusion System Component",
"entity": "fission fuel pellets"
},
{
"category": "Nuclear Fusion System Component",
"entity": "control rods"
}
]
},
{
"sentence": "The spatial power distribution of the reactor core is very flat compared with that of fission reactors.",
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{
"category": "Nuclear Fusion Device Type",
"entity": "fission reactors"
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{
"category": "Plasma region",
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},
{
"abstract": "In inertial confinement fusion implosions, tertiary reaction-in-flight processes create deuterium-tritium fusion reactions with an incident particle moving at MeV energies instead of the thermonuclear keV temperatures. Additional relativistic kinematic treatments were added to a nuclear resonance code, spect, and resulting calculations showed an upshifting of the deuterium-tritium fusion-ray pathway for MeV interactions. Using the calculated spectra, a representative reaction-in-flight-ray emission for ICF implosions was estimated.",
"title": "Deuterium-tritium fusion \nγ\n-ray spectrum at MeV energies with application to reaction-in-flight inertial confinement fusion measurements",
"URL": "http://link.aps.org/pdf/10.1103/PhysRevC.109.034003",
"fields_of_study": [
"Physics",
"Deuterium",
"Tritium",
"Nuclear physics"
],
"year_published": 2024,
"first_author": "K. D. Meaney",
"scholarly_citations_count": "NaN",
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"sentence": "In inertial confinement fusion implosions, tertiary reaction-in-flight processes create deuterium-tritium fusion reactions with an incident particle moving at MeV energies instead of the thermonuclear keV temperatures.",
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"category": "Nuclear Fusion Technique",
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"sentence": "Using the calculated spectra, a representative reaction-in-flight-ray emission for ICF implosions was estimated.",
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"category": "Physical Process",
"entity": "reaction-in-flight-ray emission"
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"category": "Nuclear Fusion Technique",
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"category": "Theory and Calculation",
"entity": "calculated spectra"
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},
{
"abstract": "A fused silica Cherenkov detector was used to measure deuterium-tritium DT gammas during a set of 52 direct-drive cryogenic experiments performed at OMEGA. The detector was calibrated using the 4.4 MeV from the first-excited state of carbon, which is produced when 14-MeV DT neutrons impinge upon a carbon puck. An approximate DT spectrum as well as neutron yields from a standard neutron time-of-flight detector at OMEGA were used to calculate a DT-to-neutron branching ratio of. Assuming an excited-state to ground-state ratio of, the measurement detailed in this work results in an approximate ground state only-to-neutron branching ratio of. This value is somewhat lower than accelerator-based measurements of the ground-state DT only.",
"title": "γ\n-to-neutron branching ratio for deuterium-tritium fusion determined using high-energy-density plasmas and a fused silica Cherenkov detector",
"URL": "NaN",
"fields_of_study": [
"Physics",
"Neutron",
"Ground state",
"Deuterium",
"Nuclear physics",
"Excited state",
"Branching fraction",
"Omega",
"Atomic physics",
"Quantum mechanics"
],
"year_published": 2023,
"first_author": "Z. L. Mohamed",
"scholarly_citations_count": 3,
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"sentence": "The detector was calibrated using the 4.4 MeV from the first-excited state of carbon, which is produced when 14-MeV DT neutrons impinge upon a carbon puck.",
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"sentence": "An approximate DT spectrum as well as neutron yields from a standard neutron time-of-flight detector at OMEGA were used to calculate a DT-to-neutron branching ratio of.",
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"sentence": "Assuming an excited-state to ground-state ratio of, the measurement detailed in this work results in an approximate ground state only-to-neutron branching ratio of.",
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"sentence": "This value is somewhat lower than accelerator-based measurements of the ground-state DT only.",
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}