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"abstract": "Abstract Fusion energy has long been considered a promising, clean, nearly inexhaustible source of energy. Power production by fusion micro-explosions of inertial confinement fusion (ICF) targets has been a long-term research goal since the invention of the first laser in 1960. The National Ignition Facility (NIF) is poised to take the next important step in the journey by beginning experiments researching ICF ignition. Ignition on NIF will be the culmination of over 30 years of ICF research on high-powered laser systems such as the Nova laser at Lawrence Livermore National Laboratory (LLNL) and the OMEGA laser at the University of Rochester, as well as smaller systems around the world. NIF is a 192-beam Nd-glass laser facility at LLNL that is more than 90% complete. The first cluster of 48 beams is operational in the laser bay, the second cluster is now being commissioned, and the beam path to the target chamber is being installed. The Project will be completed in 2009, and ignition experiments will start in 2010. When completed, NIF will produce up to 1.8\u00a0MJ of 0.35-\u03bcm light in highly shaped pulses required for ignition. It will have beam stability and control to higher precision than any other laser fusion facility. Experiments using one of the beams of NIF have demonstrated that NIF can meet its beam performance goals. The National Ignition Campaign (NIC) has been established to manage the ignition effort on NIF. NIC has all of the research and development required to execute the ignition plan and to develop NIF into a fully operational facility. NIF will explore the ignition space, including direct drive, 2 \u03c9 ignition, and fast ignition, to optimize target efficiency for developing fusion as an energy source. In addition to efficient target performance, fusion energy requires significant advances in high-repetition-rate lasers and fusion reactor technology. The Mercury laser at LLNL is a high-repetition-rate Nd-glass laser for fusion energy driver development. Mercury uses state-of-the-art technology such as ceramic laser slabs and light diode pumping for improved efficiency and thermal management. Progress in NIF, NIC, Mercury, and the path forward for fusion energy will be presented.",
"URL": "https://www.sciencedirect.com/science/article/pii/S0196890407004232",
"title": "The National Ignition Facility (NIF): A path to fusion energy",
"year_published": 2008,
"fields_of_study": [
"Inertial confinement fusion",
"Nuclear engineering",
"Engineering",
"Nova (laser)",
"Ignition system",
"Fusion power",
"National Ignition Facility",
"Mercury laser",
"Energy source",
"Thermonuclear fusion",
"Mechanical engineering"
],
"first_author": "Edward I. Moses",
"scholarly_citations_count": 42,
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"sentence": "The National Ignition Facility NIF is poised to take the next important step in the journey by beginning experiments researching ICF ignition.",
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"sentence": "Ignition on NIF will be the culmination of over 30 years of ICF research on high-powered laser systems such as the Nova laser at Lawrence Livermore National Laboratory LLNL and the OMEGA laser at the University of Rochester, as well as smaller systems around the world.",
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"sentence": "NIF is a 192-beam Nd-glass laser facility at LLNL that is more than 90 complete.",
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"sentence": "The first cluster of 48 beams is operational in the laser bay, the second cluster is now being commissioned, and the beam path to the target chamber is being installed.",
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"sentence": "Experiments using one of the beams of NIF have demonstrated that NIF can meet its beam performance goals.",
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"sentence": "The National Ignition Campaign NIC has been established to manage the ignition effort on NIF.",
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"sentence": "NIC has all of the research and development required to execute the ignition plan and to develop NIF into a fully operational facility.",
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"sentence": "NIF will explore the ignition space, including direct drive, 2 \u03c9 ignition, and fast ignition, to optimize target efficiency for developing fusion as an energy source.",
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"entity": "2 \u03c9 ignition"
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"sentence": "In addition to efficient target performance, fusion energy requires significant advances in high-repetition-rate lasers and fusion reactor technology.",
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"abstract": "The National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory (LLNL) in Livermore, CA, is now operational. The NIF is the world\u2019s most energetic laser system capable of produci...",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST11-342",
"title": "The National Ignition Facility and the Promise of Inertial Fusion Energy",
"year_published": 2011,
"fields_of_study": [
"Nuclear engineering",
"Fusion power",
"National Ignition Facility",
"National laboratory",
"Environmental science"
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"first_author": "Edward I. Moses",
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"abstract": "The Laser Inertial Fusion-based Energy (LIFE) engine design builds upon on going progress at the National Ignition Facility (NIF) and offers a near-term pathway to commercial fusion. Fusion technologies that are critical to success are reflected in the design of the first wall, blanket and tritium separation subsystems. The present work describes the LIFE engine-related components and technologies. LIFE utilizes a thermally robust indirect-drive target and a chamber fill gas. Coolant selection and a large chamber solid-angle coverage provide ample tritium breeding margin and high blanket gain. Target material selection eliminates the need for aggressive chamber clearing, while enabling recycling. Demonstrated tritium separation and storage technologies limit the site tritium inventory to attractive levels. These key technologies, along with the maintenance and advanced materials qualification program have been integrated into the LIFE delivery plan. This describes the development of components and subsystems, through prototyping and integration into a First Of A Kind power plant.",
"URL": "https://digital.library.unt.edu/ark:/67531/metadc870935/",
"title": "Fusion Technologies for Laser Inertial Fusion Energy (LIFE)",
"year_published": 2013,
"fields_of_study": [
"Inertial confinement fusion",
"Engineering",
"Process engineering",
"Laser Inertial Fusion Energy",
"National Ignition Facility",
"Blanket",
"Material selection",
"Separation (aeronautics)",
"Power station",
"Mechanical engineering",
"Coolant"
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"first_author": "K.J. Kramer",
"scholarly_citations_count": 3,
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"abstract": "Abstract The behaviour of selected alloys for superconducting magnet structures in fusion energy systems is reviewed with emphasis on the following austenitic stainless steels (AISI grades 304, 310S and 316), nitrogen-strengthened austenitic stainless steels (types 304LN, 316 LN and 21Cr\ue5f86Ni\ue5f89Mn) and aluminum alloys (grades 5083, 6061 and 2219). The mechanical and physical properties of the selected alloys at 4 K are reviewed. Welding, the properties of weldments, and other fabrication considerations are briefly discussed. The available information suggests that several commercial alloys have adequate properties at 4 K and sufficient fabrication characteristics for the large magnet structures needed for fusion energy systems.",
"URL": "https://www.sciencedirect.com/science/article/pii/0029549380901259",
"title": "Structural alloys for superconducting magnets in fusion energy systems",
"year_published": 1980,
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"Magnet",
"Superconducting magnet",
"Metallurgy",
"Materials science",
"Welding",
"Fusion power",
"Aluminium",
"Austenite"
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"first_author": "H.I. McHenry",
"scholarly_citations_count": 18,
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"abstract": "S&D\u2019s 10th Anniversary is also an exciting time for ITER, with many of its goals coming to fruition. Todd K. Harding explores how this scientific facility overcame barriers and now serves as a great example of international cooperation.",
"URL": "NaN",
"title": "ITER: International Fusion Energy Science and Diplomacy \u2013 Realized",
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"Energy (signal processing)",
"Nuclear engineering",
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"abstract": "The cooling arm plays an important role in the production process of fusion energy. The structure is designed with 16 fingers and is simulated by the finite-element method. The (111) crystal orientation silicon is deployed to fabricate a cooling arm, because of its isotropic Young's modulus. It can make the fingers generate a uniform force. The silicon also has a large thermal conductivity of 2400 W/mK measured by a Gifford-McMahon cooler, which contributes to heat transfer. The cooling arm is fabricated by the microfabrication process, and it has a high sidewall vertical degree of 90 \u00b1 0.5\u00b0 measured by scanning electron microscopy. The mechanical testing result shows that the maximum stress of the clamping arm was 0.209 GPa when it was in gripping state. The maximum stress is far smaller than the yield strength of 7 GPa of silicon material.",
"URL": "https://digital-library.theiet.org/content/journals/10.1049/mnl.2012.0964",
"title": "Microfabrication of cooling arm for fusion energy source application",
"year_published": 2013,
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"abstract": "The Kudowa Summer School \"Towards Fusion Energy\" takes place every two years in summer, usually in June, in Kudowa-Zdr\u00f3j: a small resort city at the Polish-Czech border and is organized by the Institute of Plasma Physics and Laser Microfusion, Warsaw, Poland. Multinational audience, mostly PhD students, as well as Master students and young scientists from all over the world, have an opportunity to gather in order to broaden their knowledge of plasma and fusion physics, participating in lectures presented by outstanding and world-renowned lecturers working in the field of nuclear fusion.",
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"abstract": "We describe our recent efforts demonstrating direct current sintering parameters appropriate to mimic near-identical microstructure to optimize reduced activation ferritic martensitic \u201ccastable nanostructured alloy\u201d. The fabrication process is presented, and through a combination of computational thermodynamics, multimodal characterization, and mechanical testing we confirm that sintering may be used to produce relevant castable nanostructured alloy (CNA). Our success in demonstrating the applicability of sintering to CNA fabrication opens the opportunity to fabricate functionally graded first wall tile structures or other complicated structures with demanding high-temperature performance, as example fusion high heat flux components.",
"URL": "NaN",
"title": "Sintered nanostructured alloys for advanced fusion energy applications",
"year_published": 2023,
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"Sintering",
"Materials science",
"Microstructure",
"Alloy",
"Fusion",
"Characterization (materials science)",
"Metallurgy",
"Process (computing)",
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"Fusion power",
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"Plasma",
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"Linguistics",
"Philosophy",
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"abstract": "Recent progress in laser driven implosion is reviewed. Improvements in the uniformity of irradiation by laser beams on fuel pellets have achieved quantitative progress in implosion performance. The recent results of the direct drive\u2013central ignition experiments give us confidence in achieving fusion ignition, burning and energy gain using a multi-beam megajoule laser with full implementation of beam smoothing techniques. Fast ignition research is also reviewed, which could give us a higher energy gain with lower laser energy. The science and technology of laser fusion power plants are beginning to attract wider attention, as forming the road map to achieve commercial power plants for cleaner, safer and abundant fusion energy.Corrections were made to this article on 28 April 2004",
"URL": "http://dx.doi.org/10.1088/0034-4885/67/3/r04",
"title": "Laser driven inertial fusion energy: present and prospective",
"year_published": 2004,
"fields_of_study": [
"Inertial confinement fusion",
"Nuclear engineering",
"Physics",
"Fusion ignition",
"Ignition system",
"Nanotechnology",
"Energy (signal processing)",
"Implosion",
"Fusion power",
"Pellets",
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"first_author": "S. Nakai",
"scholarly_citations_count": 99,
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"abstract": "Estimates of energy supply versus consumption indicate the middle of this century as the critical point when world energy supply will no longer keep pace with the demand. The demand grows inexorably because of both the world population growth as well as the growth of average per capita energy consumption. Technological and economic progress are closely correlated with per capita energy consumption. Hence the inadequacy of energy supplies will limit the progress of human civilization, stifling its soaring spirit. Conservationism, making incremental improvements in this situation, is completely inadequate. What is needed is a giant step\u2014the development of a new, limitless, clean source of energy\u2014nuclear fusion energy. Nuclear fusion technology, when perfected to fusion-burn only deuterium, will have a fuel supply lasting millions of year, even with continuing energy consumption growth as in the past. Intensive efforts in five decades of Tokamak research has advanced the fusion product up by 107 times, to the point when breakeven is only a step away. The next step necessarily involves international collaboration on an unprecedented scale in ITER\u2014the International Thermonuclear Experimental Reactor, on which work has started in Cadarache France. ITER and later Demo are envisioned to bring online the first commercial nuclear fusion energy reactor by 2050. Using this as the starting point and the history of the uptake of nuclear fission reactors as a guide, a scenario is described here which depicts a not unreasonable rapid take up of nuclear fusion energy starting after the middle of this century. Just into the next century fusion energy should be able to take up the slack and allow Mankind to continue its progress and growth. Because the development of fusion energy is such a complex technological task it is probable that there will be several decades when the constraints of energy shortage will be severely felt as shown by the flattening of the energy consumption from around 2040 to 2100. Such a period of stagnation seems unavoidable even with the envisaged development and rapid adoption of fusion energy. On the other hand without nuclear fusion energy the scenario depicts a severe downturn unavoidably in the fortunes of Mankind with world population shrinking below 5 billion and eventually even lower.",
"URL": "https://link.springer.com/article/10.1007/s10894-011-9390-7",
"title": "Nuclear Fusion Energy\u2014Mankind\u2019s Giant Step Forward",
"year_published": 2011,
"fields_of_study": [
"Per capita",
"Economics",
"Nuclear physics",
"Fusion power",
"Energy supply",
"Energy consumption",
"World energy consumption",
"Market economy",
"World population",
"Nuclear fusion",
"Thermonuclear fusion"
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"first_author": "Sing Lee",
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{
"abstract": "Continuous operation of a tokamak for fusion energy has clear engineering advantages but requires conditions beyond those sufficient for a burning plasma. The fusion reactions and external sources must support both the pressure and the current equilibrium without inductive current drive, leading to demands on stability, confinement, current drive, and plasma-wall interactions that exceed those for pulsed tokamaks. These conditions have been met individually, and significant progress has been made in the past decade to realize scenarios where the required conditions are obtained simultaneously. Tokamaks are operated routinely without disruptions near pressure limits, as needed for steady-state operation. Fully noninductive sustainment with more than half of the current from intrinsic currents has been obtained for a resistive time with normalized pressure and confinement approaching those needed for steady-state conditions. One remaining challenge is handling the heat and particle fluxes expected in a steady-state tokamak without compromising the core plasma performance.",
"URL": "https://meetings.aps.org/Meeting/DPP09/Session/AR1.1",
"title": "Realizing Steady State Tokamak Operation for Fusion Energy",
"year_published": 2009,
"fields_of_study": [
"Tokamak",
"Nuclear engineering",
"Physics",
"Current (fluid)",
"Fusion power",
"Steady state",
"Continuous operation",
"Resistive touchscreen",
"Nuclear fusion",
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"first_author": "T. C. Luce",
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{
"abstract": "Long-term limits to growth in energy will be imposed not by inability to expand supply, but by the rising environmental and social costs of doing so. These costs will therefore be central issues in choosing long-term options. Fusion, like solar energy, is not one possibility but many, some with very attractive environmental characteristics and others perhaps little better in these regards than fission. None of the fusion options will be cheap, and none is likely to be widely available before the year 2010. The most attractive forms of fusion may require greater investments of time and money to achieve, but they are the real reason for wanting fusion at all.",
"URL": "https://www.science.org/doi/abs/10.1126/science.200.4338.168",
"title": "Fusion energy in context: its fitness for the long term.",
"year_published": 1978,
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"Cost\u2013benefit analysis",
"Business",
"Nuclear physics",
"Fusion power",
"Context (language use)",
"Economic analysis",
"Light nucleus",
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"first_author": "John P. Holdren",
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"abstract": "Abstract On the road toward fusion energy, ITER is the first fusion facility which will have enough radioactive inventory to be potentially dangerous for the public and the environment. As such, ITER has a licensed nuclear facility status and its operator, ITER Organization, has to define technical, organizational and human provisions such as to prevent or adequately limit the risks of accidents as well as the disadvantages (exposure to ionizing radiation, environmental releases and waste) that the facility presents. All the facilities which will be created after ITER, in order to develop fusion energy (DEMO\u2026) then to use it (PROTO\u2026), will clearly also be facilities for which the nuclear safety aspects will have to be taken into account. This paper describes the safety characteristics of fusion facilities, the state of progress of the ITER safety demonstration regarding these characteristics and their possible evolutions for the facilities succeeding ITER on the road to fusion energy.",
"URL": "https://www.sciencedirect.com/science/article/pii/S0920379618307609",
"title": "Nuclear safety aspects on the road towards fusion energy",
"year_published": 2019,
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"abstract": "Experimental and theoretical techniques to produce spectral data for fusion energy have evolved greatly since the 1970s. Light sources have progressed from energetic sparks and laser-produced plasmas to electron beam ion traps (EBITs) and tokamaks themselves. Theory has advanced from non-relativistic Hartree\u2013Fock to fully relativistic Dirac\u2013Fock calculations and detailed collisional-radiative (CR) modeling of plasmas with codes generating large numbers of cross sections and other atomic data. A great deal of work of late has focused on tungsten, which although originally thought to be not usable for high-temperature machines, has now been selected to play an important role in ITER, the international tokamak reactor to be built in France. Work on tungsten from various laboratories and recent results for highly ionized W from the EBIT at the National Institute of Standards and Technology are discussed.",
"URL": "https://ui.adsabs.harvard.edu/abs/2009PhST..134a4023R/abstract",
"title": "Spectral data for fusion energy: from W to W",
"year_published": 2009,
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"USable",
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"first_author": "Joseph Reader",
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"abstract": "The goal of the HiLASE project is to design and optimize parameters for 100 J/ 10 Hz Yb:YAG laser amplifiers that are scalable to the kJ regime. The HiLASE power amplifier design is based on a cryogenic, gas-cooled multi-slab concept. Simulation results of the 10 J pre-amplifier agree very well with experimental measurements. In order to fulfil the very demanding requirements, which include wall-plug efficiency > 12% and repetition rates up to 10 Hz, HiLASE and RAL teams are closely working together and developing the approach described here.",
"URL": "http://ui.adsabs.harvard.edu/abs/2016JPhCS.688a2060L/abstract",
"title": "HiLASE: a scalable option for Laser Inertial Fusion Energy",
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"Engineering",
"Amplifier",
"Electronic engineering",
"Laser Inertial Fusion Energy",
"Laser amplifiers",
"Plasma confinement",
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"abstract": "A brief introduction to the inertial fusion energy (IFE) and its fundamental requirements for beamdrivers is presented, and then the progress of high-average-power-laser developed for IFE isemphasized. Finally, other issues related to IFE and the timetable are also presented.",
"URL": "http://en.cnki.com.cn/Article_en/CJFDTOTAL-JGDJ200609012.htm",
"title": "Research Progress of Laser Drivers for Inertial Fusion Energy",
"year_published": 2006,
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"Aerospace engineering",
"Nanotechnology",
"Inertial frame of reference",
"Fusion power",
"Computer science",
"Laser"
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"first_author": "Sui Zhan",
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"abstract": "Shock-ignited inertial fusion targets are studied by one dimensional and two-dimensional numerical simulations. Most of the study refers to the simple all-DT HiPER baseline target (imploded mass of 0.29 mg); both the reference laser wavelength \u03bb = 0.35 \u03bcm, and \u03bb = 0.25 \u03bcm are considered. The target achieves 1D gain about 80 (120) with total laser energy of 260 kJ (180 kJ) at \u03bb = 0.35 \u03bcm (0.25 \u03bcm). Operating windows for the parameters of the laser ignition spike are described. According to preliminary simulations, gain 80\u2013100 is also obtained by a scaled target (imploded mass of 1.8 mg) driven by 1.5 MJ of green laser light (0.53 \u03bcm). Two dimensional simulations indicate robustness to irradiation nonuniformities, and high sensitivity to target mispositioning. This can however be reduced by increasing the power of the ignition spike.",
"URL": "https://www.epj-conferences.org/articles/epjconf/abs/2013/20/epjconf_ifsa2011_01005/epjconf_ifsa2011_01005.html",
"title": "Studies on shock ignition targets for inertial fusion energy",
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"abstract": "The inertial confinement fusion (ICF) philosophy is based on high compression. The reasoning is that (a) it is cheaper (energetically) to compress than to heat and (b) nuclear reactions are proportional to density square, therefore the more you compress the better you are in ICF. Of course the only limitations of compression are the hydrodynamic instabilities (like Rayleigh-Taylor, etc). Many of the references in the literature require extremely high compression and in particular the pB11 needs extremely huge compressions. In this paper it is shown that there is an optimum of compression, namely gain G is maximum for a definite compression. The value of this density (for a given fuel mass and particular ICF scheme) depends on the equation of state (EOS). We calculate this value for fast ignition (FI) schemes and compare it with the central spark ignition (CSI) model. The gain calculations are based on the ideal gas for the ions and the Fermi-Dirac EOS for the electrons with an effective alpha, as usually suggested from simulations. The \u201coptimum compression\u201d idea is easily understood from the following argument: From EOS data one needs an infinite energy to compress to an infinite density. Since the energy output is finite it is clear that G is zero for infinite compression. On the other hand for normal density with small fuel mass (~ few mg) the gain is also zero. Therefore a maximum should exist somewhere. For the deuterium-tritium fuel with a mass of few mg one gets an optimum at few hundred g/cc. If you compress more then the gain is going down. So there is a desired maximum compression fixed by EOS. Last but not least, bremsstrahlung losses in degenerate plasma are discussed and the clean fusion (i.e., without neutrons) of proton\u00a0+\u00a0B11\u00a0\u2192\u00a04\u03b1 is analyzed.",
"URL": "http://ui.adsabs.harvard.edu/abs/2007LPB....25..585E/abstract",
"title": "Equation of state and optimum compression in inertial fusion energy",
"year_published": 2007,
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"first_author": "Shalom Eliezer",
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"abstract": "Global warming due to rapid greenhouse gas (GHG) emissions is one of the present-day crucial problems, and fusion reactors are expected to be abundant electric power generation systems to reduce human GHG emission amounts. To search for an environmental-friendly and economical fusion reactor system, comparative system studies have been done for several magnetic fusion energy reactors, and have been extended to include inertial fusion energy reactors. We clarify new scaling formulae for the cost of electricity and GHG emission rate with respect to key design parameters, which might be helpful in making a strategy for fusion research development. Comparisons with other conventional electric power generation systems are carried out taking into account the introduction of GHG taxes and the application of the carbon dioxide capture and storage system to fossil power generators.",
"URL": "http://iopscience.iop.org/article/10.1088/0029-5515/51/10/103004/meta",
"title": "Environmental and economic assessments of magnetic and inertial fusion energy reactors",
"year_published": 2011,
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"Electricity generation",
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"first_author": "Kozo Yamazaki",
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"abstract": "The Target Fabrication Facility (TFF) of an IFE power plant must supply about 500,000 targets per day. The targets are injected into the target chamber at a rate of 5-10 Hz and tracked precisely so the driver beams can be directed to the target. The feasibility of developing successful fabrication and injection methodologies at the low cost required for energy production (about $0.25/target, about 10 4 less than current costs) is a critical issue for inertial fusion. To help identify major cost factors and technology development needs, we have utilized a classic chemical engineering approach to the TFF. The analyses assume an nth-of-a-kind TFF and utilize standard industrial engineering cost factors. The results indicate that the direct drive target can be produced for about $0.16 each. Iterations are still underway for the indirect drive target. These cost analyses assume that the process development is accomplished to allow scaling of current laboratory methods to larger sizes, while still meeting target specifications. A development program is underway at various laboratories to support this scale-up.",
"URL": "https://www.ans.org/pubs/journals/fst/a_347",
"title": "Demonstrating a Cost-Effective Target Supply for Inertial Fusion Energy",
"year_published": 2003,
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"abstract": "AbstractMagnetically confined fusion plasmas generate energy from deuterium-tritium (DT) fusion reactions that produce energetic 3.5\u00a0MeV alpha particles and 14\u00a0MeV neutrons. Since the DT fusion reaction rate is a strong function of plasma density, an efficient fueling source is needed to maintain high plasma density in such systems. Energetic ions in fusion plasmas are able to escape the confining magnetic fields at a much higher rate than the fusion reactions occur, thus dictating the fueling rate needed. These lost ions become neutralized and need to be pumped away as exhaust gas to be reinjected into the plasma as fuel atoms.The technology to fuel and pump fusion plasmas has to be inherently compatible with the tritium fuel. An ideal holistic solution would couple the pumping and fueling such that the pump exhaust is directly fed back into pellet formation without including impurity gases. This would greatly reduce the processing needs for the exhaust. Concepts to accomplish this are discussed along wi...",
"URL": "https://www.tandfonline.com/doi/abs/10.1080/15361055.2017.1288421",
"title": "Tritium Aspects of Fueling and Exhaust Pumping in Magnetic Fusion Energy",
"year_published": 2017,
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"first_author": "Larry R. Baylor",
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"abstract": "We have been developing a high average-power laser system for science and industry applications that can generate an output of 20 J per pulse at 10-Hz operation. Water-cooled Nd:glass zig-zag slab is pumped with 803-nm AlGaAs laser-diode modules. To efficiently extract energy from the laser medium, the laser beam alternately passes through dual zig-zag slab amplifier modules. Twin LD modules equipped on each slab amplifier module pump the laser medium with a peak power density of 2.5 kW/cm 2 . In high power laser system, thermal load in the laser medium causes serious thermal effects. We arranged cladding glasses on the top and bottom of the laser slab to reduce thermal effects.",
"URL": "https://www.spiedigitallibrary.org/conference-proceedings-of-spie/6101/1/Development-of-thermally-controlled-HALNA-DPSSL-for-inertial-fusion-energy/10.1117/12.645644.full",
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"abstract": "The International Atomic Energy Agency has been promoting international activity and collaboration related to the use of inertial fusion confinement schemes for energy production for many years. Thorough review of inertial fusion research and a detailed analysis of future prospects has been conducted. Inertial Fusion Energy is now approaching the turning point in the long history from physics oriented research to fusion energy oriented development. The programme of the International Atomic Energy Agency reflects, to some extent, this development.",
"URL": "http://ui.adsabs.harvard.edu/abs/2008JPhCS.112c2051M/abstract",
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"abstract": "Propagation of a laser light through regions of an underdense plasma is an active research topic in laser fusion. In particular, a large effort has been invested in studies of stimulated Raman scattering (SRS) and stimulated Brillouin scattering (SBS), which can reflect laser energy and produce energetic particles to preheat a fusion energy target. Experiments, theory, and simulations agree on a complex interplay between various laser-plasma instabilities. By particle-in-cell simulations of an underdense electron plasma, apart from the standard SRS, a strong backscattering was found near the electron plasma frequency at densities beyond the quarter critical. This novel instability, recognized in recent experiments as stimulated laser scattering on a trapped electron-acoustic mode (SEAS), is absent from a classical theory of laser-parametric instabilities. A parametric excitation of SEAS instability is explained by a three-wave resonant decay of the incident laser light into a standing backscattered wave and a slow trapped electron-acoustic wave ({omega} <{omega}{sub p}). Large SEAS pulsations, eventually suppressed by relativistic heating of electrons, are observed in these simulations. This phenomenon seems relevant to future hohlraum target and fast ignition experiments.",
"URL": "https://inis.iaea.org/Search/search.aspx?orig_q=RN:38018047",
"title": "On Stimulated Scattering of Laser Light in Inertial Fusion Energy Targets",
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"Atomic physics",
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"abstract": "High-energy electron beam pumped krypton fluoride (KrF) gas lasers are an attractive choice for inertial fusion energy (IFE). Their short wavelength and demonstrated high beam uniformity optimizes the laser-target physics, and their pulsed power technology scales to a large system. This paper presents the principals of this type of laser and the progress toward developing technologies that can meet the IFE requirements for repetition rate (5 Hz), efficiency (>6%), and durability (>3/spl times/10/sup 8/ shots). The Electra laser at the Naval Research Laboratory (NRL) has produced >500 J of laser light in short 5-Hz bursts. Research on Electra and the NRL Nike laser (3000 J, single shot) has shown that the overall efficiency should be greater than 7%. This is based on recent advances in electron beam stabilization and transport, electron beam deposition, KrF laser physics, and pulsed power. The latter includes the development of a new solid-state laser triggered switch that will be the basis for a pulsed power system that can meet the IFE requirements for efficiency, durability, and cost. The major remaining challenge is to develop long-lived hibachi foils (e-beam transmission windows). Based on recent experiments, this may be achievable by periodically deflecting the laser gas.",
"URL": "https://dblp.uni-trier.de/db/journals/pieee/pieee92.html#SethianMGLKOHFW04",
"title": "Electron beam pumped krypton fluoride lasers for fusion energy",
"year_published": 2004,
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"Optics",
"Beam (structure)",
"Materials science",
"Fusion power",
"Excimer laser",
"Nike laser",
"Laser science",
"Laser",
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"first_author": "John D. Sethian",
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"abstract": "In inertial confinement fusion, pellets of deuterium tritium fuel are compressed and heated to the conditions where they undergo fusion and release energy. The target gain (ratio of energy released from the fusion reactions to the energy in the drive source) is a key parameter in determining the power flow and economics of an inertial fusion energy (IFE) power plant. In this study, the physics of gain is explored for laser-direct-drive targets with driver energy at the megajoule scale. This analysis is performed with the assumption of next-generation laser technologies that are expected to increase convergent drive pressures to over 200 Mbar. This is possible with the addition of bandwidth to the laser spectrum and by employing focal-spot zooming. Simple physics arguments are used to derive scaling laws that describe target gain as a function of laser energy, adiabat, ablation pressure, and implosion velocity. Scaling laws are found for the unablated mass, ablation pressure, areal density, implosion velocity, and in-flight aspect ratio. Those scaling laws are then used to explore the design space for IFE targets.",
"URL": "https://pubs.aip.org/aip/pop/article-pdf/doi/10.1063/5.0167405/18288538/012702_1_5.0167405.pdf",
"title": "The physics of gain relevant to inertial fusion energy target designs",
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"abstract": "Each claim made by DOE is stated then the author gives his arguments against this claim. Subjects discussed are power generation, performance, by-products, radioactive wastes, hazardous materials, radiation hazards, thermal pollution, tritium fuel, economics, proof of principle, industrial support, energy independence, and Congression directives. These arguments and claims pertain to the tokamak. 79 refs.",
"URL": "http://www.osti.gov/scitech/biblio/6400141-claims-compared-realities-doe-fusion-energy-program",
"title": "25 claims compared to realities of the DOE's fusion energy program",
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"abstract": "The advent of a fusion energy industry is being strongly supported by academics and universities, with the majority of fusion companies launching out of universities. Universities also play critical roles in technical innovation, workforce development, and independent arbiters of science and technology. The ability of the US academic landscape to support and grow the fusion energy sector is analyzed via a numerical distribution of full time faculty engaged in fusion and plasma. This data is compared to university support in two existing technology-driven industries: nuclear and aeronautics. This comparison clearly shows that the university system requires not only significant absolute growth but also a wider distribution of faculty at universities and across the required disciplines.",
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"abstract": "A consistent method for the comparison of environmental, safety, and health (ES&H) characteristics of fusion power plant designs is developed. Such comparisons enable identification of trends in fusion ES&H characteristics and can be used to increase the likelihood of fusion achieving its full potential with respect to ES&H characteristics. A large number of radiological hazard indexes are defined in three different categories of hazard: accidents, occupational and routine exposures, and waste disposal. Using a consistent set of computer codes, data libraries, and assumptions, these radiological hazard indexes are calculated and compared for five inertial and two magnetic fusion energy power plant designs. The results of the analysis are threefold: The utility of low-activation materials (LAMs) is confirmed, the tremendous potential for the use of thick-liquid system for first-wall protection is validated, and the strong need for materials that can last for the lifetime of the power plant is shown. The conservative radionuclide release fractions that are used show that all but one of the designs has only a minute chance of producing any early fatalities during an accident. The need for remote maintenance in most designs is confirmed, and the possibility of disposing of most fusion wastes via shallow land burial (if the methodology ofcurrent regulations is applied to fusion wastes) is shown. The need for more research in LAMs and for the experimental measurement of radionuclide release fractions under accident conditions is emphasized.",
"URL": "https://core.ac.uk/display/71170866",
"title": "Inertial fusion energy : A clearer view of the environmental and safety aspects",
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"abstract": "Modern high-power lasers can generate extreme states of matter that are relevant to astrophysics, equation-of-state studies and fusion energy research. Laser-driven implosions of spherical polymer shells have, for example, achieved an increase in density of 1,000 times relative to the solid state. A new laser technology \u2018ultra-intense\u2019 laser is now opening a new ground of the laser fusion research, which is called as fast ignition. During the last several years, we have extensively studied elementary physics relevant to the fast ignitor. Based on these results, we have succeeded enforced heating of imploded plasmas with a 100 TW laser as the first demonstration of this new approach. The experimental result implies the future possibility of breakeven and ignition with significantly small laser energies. This new approach provides a route toefficientfusionenergy production.",
"URL": "http://ui.adsabs.harvard.edu/abs/2002JPFR...78..792K/abstract",
"title": "Progress of advanced fusion energy studies with ultra-intense lasers",
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"abstract": "AbstractTracing the history of terrestrial fusion energy to a giant multinational experimental fusion facility under construction reveals a series of consequential failures, re\u2010evaluations of once defunct designs, but also persistence. To account for how this vast enterprise, dogged by failure, endures, I suggest that different ontological narratives re\u2010orientate the enterprise both temporally and vis\u2010\u00e0\u2010vis different forms and valences of failure. Thus the rhetoric of mission\u2010driven project vies with that of open\u2010ended, present\u2010focused experiment: the former is positioned as the crucial solution to the threat of climate change; the latter \u2018bakes in\u2019 virtuous failure as integral to creative practice. Visionary promise moves to a focus on the meanwhile. Finally, the sheer unfurling size to which attention is constantly drawn offers a disorientating spectacle, denying perspective or closure and acting to suspend judgements of failure.",
"URL": "https://onlinelibrary.wiley.com/doi/pdfdirect/10.1111/1467-9655.13905",
"title": "Suspending failure: temporalities, ontologies, and gigantism in fusion energy development",
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"Perspective (graphical)",
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"abstract": "This paper describes a prospect toward electric power production by the Fusion energy. In the first part of the paper, a principle of TOKAMAK system which is the successful magnetic-confinement-systems for fusion reactors are shown, and then the ITER project based on TOKAMAK and the present status of ITER is reviewed. In the remainder of the paper, a roadmap for fusion energy and conceptual designs of Demonstration reactors are briefly described.",
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"title": "A prospect on the demonstration of electric power production from fusion energy",
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"abstract": "A summary of negative ion development work being presently undertaken at the Culham Centre for Fusion Energy is given. The small negative ion facility has an RF driven volume ion source with beam extraction at energies up to 30 keV. The extracted beam of H\u2212 ions has an associated co-extracted electron beam with an electron to ion ratio of <1 over the whole range of operating parameters. In order to understand this performance spectroscopic investigations have been undertaken using the Balmer series line to determine the electron temperature. In addition a 1D fluid model of an RF driven ion source is also under development. This model is based on a successful model for both arc discharge positive and negative ion sources. Additional system studies of neutral beam injection systems for future fusion machines beyond ITER are being carried out. This is required to understand the limits of various neutralisation and energy recovery systems in order to maximise overall electrical efficiency.",
"URL": "https://iopscience.iop.org/article/10.1088/1367-2630/aa4fa1/pdf",
"title": "Negative ion research at the Culham Centre for Fusion Energy (CCFE)",
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"Fusion power",
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"abstract": "Magnetic confinement fusion (MCF) and inertial confinement fusion (ICF) are two typical approaches of controlled fusion. The energy gain of magnetic confinement fusion achieved unity already, and inertial confinement fusion also made a big progress recently. However, the parameter spaces of two methods are different with 11 magnitudes, and their facilities are very large with fancy cost. Magneto-inertial fusion (MIF) combines both features of MCF and ICF, whose parameter space intermediates between the two extremes of MCF and ICF. The capital cost of MIF is much lower than either of the two, and it has large potential for commercial applications. With advantages of low cost, compact facility, and short time of construction, MIF draws more and more attention recently. In this paper, the status and recent progress of MIF research will be introduced.",
"URL": "https://engine.scichina.com/publisher/scp/journal/SSPMA/46/11/10.1360/SSPMA2016-00279?slug=full%20text",
"title": "Magneto-inertial fusion: A new approach towards fusion energy",
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"title": "NIF success gives laser fusion energy a shot in the arm",
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"abstract": "The new possibility of side-on laser ignition of p-11B with negligible radioactivity encouraged to study the fusion of solid state p-7Li fuel that again turns out to be only about 10 times more difficult than the side-on ignition of solid deuterium-tritium using petawatt-picosecond laser pulses at anomalous interaction conditions if very high contrast ratio. Updated cross sections of the nuclear reaction are included.",
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"abstract": "The Laser Inertial Fusion Energy (LIFE) concept is being designed to operate as either a pure fusion or hybrid fusion-fission system. The present work focuses on the pure fusion option. A key component of a LIFE engine is the fusion chamber subsystem. It must absorb the fusion energy, produce fusion fuel to replace that burned in previous targets, and enable both target and laser beam transport to the ignition point. The chamber system also must mitigate target emissions, including ions, x-rays and neutrons and reset itself to enable operation at 10-15 Hz. Finally, the chamber must offer a high level of availability, which implies both a reasonable lifetime and the ability to rapidly replace damaged components. An integrated design that meets all of these requirements is described herein.",
"URL": "https://digital.library.unt.edu/ark:/67531/metadc831162/m2/1/high_res_d/1028880.pdf",
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"abstract": "The primary purpose of the workshop was to gather input from the inertial confinement fusion (ICF) laboratories, private industry, and universities on the potential use of the NIF to conduct experiments in support of the development of IFE. To accomplish this, we asked the over 60 workshop participants to identify key credibility and development issues for IFE in four areas Target Physics --Issues related to the design and performance of targets for IFE; Chamber Dynamics -- Issues in IFE chambers resulting from the deposition of x-rays and debris; Inertial Fusion Power Technology -- Issues for energy conversion, tritium breeding and processing, and radiation shielding; interactions of neutrons with materials; and chamber design; Target System -- Issues related to automated, high-production-rate manufacture of low-cost targets for IFE, target handling and transport, target injection, tracking, and beam pointing. These topics are discussed in this report.",
"URL": "http://ui.adsabs.harvard.edu/abs/1994tfe..meetQ..19T/abstract",
"title": "Use of the National Ignition Facility for the Development of Inertial Fusion Energy",
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"abstract": "AbstractFocused Energy is a new startup company with the goal of developing laser-driven inertial fusion energy for electrical power production. The company combines the results from decades of fundamental research in inertial confinement fusion at universities and national laboratories with the flexibility and the speed of a startup company. Focused Energy has chosen the direct-drive, proton fast ignition approach to reach ignition, burn and high gain as the most promising approach. Located in Austin/US and Darmstadt/Germany, supported by the science community and private investment Focused Energy is paving the way to inertial fusion energy combining the best skill set and state-of-the-art technology from both sides of the Atlantic Ocean. In this paper we discuss the details and reasoning for the approach and the technical directions we have chosen. We will outline our roadmap for getting to a fusion pilot plant in the mid to late 2030s.\n",
"URL": "https://link.springer.com/content/pdf/10.1007/s10894-023-00363-x.pdf",
"title": "Focused Energy, A New Approach Towards Inertial Fusion Energy",
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"Aerospace engineering",
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"abstract": "Bernard Bigot sees management of the seven-party international effort as a greater challenge than the technological demands.",
"URL": "http://www.osti.gov/scitech/biblio/22410506-new-iter-head-confident-fusion-energy-project-succeed",
"title": "New ITER head is confident the fusion energy project will succeed",
"year_published": 2015,
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"abstract": "Science research in general and magnetic fusion research in particular continue to grow in size and complexity resulting in a concurrent growth in collaborations between experimental sites and laboratories worldwide. The simultaneous increase in wide area network speeds has made it practical to envision distributed working environments that are as productive as traditionally collocated work. In computing power, it has become reasonable to decouple production and consumption resulting in the ability to construct computing grids in a similar manner as the electrical power grid. Grid computing, the secure integration of computer systems over high speed networks to provide on-demand access to data analysis capabilities and related functions, is being deployed as an alternative to traditional resource sharing among institutions. For human interaction, advanced collaborative environments are being researched and deployed to have distributed group work that is as productive as traditional meetings. The DOE Scientific Discovery through Advanced Computing Program initiative has sponsored several collaboratory projects, including the National Fusion Collaboratory Project, to utilize recent advances in grid computing and advanced collaborative environments to further research in several specific scientific domains. For fusion, the collaborative technology being deployed is being used in present day research and is also scalable to future research, in particular, to the International Thermonuclear Experimental Reactor experiment that will require extensive collaboration capability worldwide. This paper briefly reviews the concepts of grid computing and advanced collaborative environments and gives specific examples of how these technologies are being used in fusion research today.",
"URL": "http://ui.adsabs.harvard.edu/abs/2005PhPl...12e8104S/abstract",
"title": "Grid computing and collaboration technology in support of fusion energy sciencesa)",
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"abstract": "The characterization of a high current, relativistic electron beam, designated the Super Pinch electron beam, has been performed using compact pulsed-power accelerators of various architectures with a novel diode geometry. The Thunderbird accelerator has an initial $1.5\\text{\\ensuremath{-}}\\ensuremath{\\mu}\\mathrm{s}$ rise time and 150-kA peak current. The drive voltage is compressed to produce a 12-ns 500-kV voltage pulse generating a $\\ensuremath{\\sim}40\\text{\\ensuremath{-}}\\mathrm{kA}$ electron beam, which apparently exceeds the Alv\\'en current limit although the useful current at small radius is an order of magnitude less. Using an insulated hollow cathode with a 0.5-cm anode-cathode gap, the large current is enabled by the evolution of plasma from the dielectric sleeve enveloping the cathode and a 0.5-mm wire anode. Post-shot recovery of the anode target and measurements of its deformation and damage allow an evaluation of the enhanced electron-beam focusing whereby significant beam energy is delivered to the record small, microscopic volume inside the anode target. The electron beam is seen to have conditions favorable to those needed to ignite compressed fuel in inertial confinement fusion. These results motivated a deeper insight using theoretical modeling with hybrid particle-in-cell codes. The modeling presented in this paper shows an electron beam radius of $<10\\text{ }\\text{ }\\ensuremath{\\mu}\\mathrm{m}$ containing a current of 3--6 kA or $>500\\text{ }\\text{ }\\mathrm{MA}/{\\mathrm{cm}}^{2}$ current density. Scaling up the accelerator, such preferred focusing, target penetration, and affordability of the pulsed power generated electron beams open a new opportunity for the application of the mainstream pulsed power devices in the research and development of fusion energy.",
"URL": "http://link.aps.org/pdf/10.1103/PhysRevAccelBeams.24.120401",
"title": "Dynamics of the super pinch electron beam and fusion energy perspective",
"year_published": 2021,
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"Electron",
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"Atomic physics",
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"abstract": "In the High Average Power Laser program, we have developed an integrated target tracking and engagement system designed to track an inertial fusion energy target traveling 50-100 m/s in three dimensions and to steer driver beams so as to engage it with \u00b120 \u03bcm accuracy. The system consists of separate axial and transverse detection techniques to pre-steer individual beamlet mirrors, and a final fine-correction technique using a short-pulse laser \"glint\" from the target itself. Transverse tracking of the target uses the Poisson spot diffraction phenomenon, which lies exactly on axis to the centroid of the target. The spot is imaged on a digital video camera and its centroid is calculated in \u223c10 ms with 5 \u03bcm precision. In our tabletop demonstration, we have been able to continuously track a target falling at 5 m/s and provide a fast steering mirror with steering commands. We are on the verge of intercepting the target on-the-fly and of verifying the accuracy of engagement. Future work entails combining transverse tracking, axial tracking, triggering and the final \"glint\" system. We also will implement a verification technique that confirms successful target engagement with a simulated driver beam. Results and integration progress are reported.",
"URL": "http://aries.ucsd.edu/LIB/REPORT/JOURNAL/FST/CarlsonTOFE07.pdf",
"title": "Target Tracking and Engagement for Inertial Fusion Energy - A Tabletop Demonstration",
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"abstract": "The big lasers for inertial fusion (NIF or LMJ) \nmay be used with 2 to 3 times larger pulse energy if instead \nof the third harmonics, the fundamental wavelength is applied. \nA necessary condition especially for direct drive is then \nto suppress the stochastic (15 ps) pulsation of the interaction \nas the basic obstacle of anomalous interaction. The experiments \nby Maddever and the numerical analysis using the genuine \ntwo-fluid model resulted in the knowledge that appropriate \napplication of smoothing is necessary to suppress primarily \nthe pulsation and, to a lesser extent, the self-focusing \nand filamentation. With these larger laser pulses, fusion \ngains of 35 and above can be reached suing the very uncomplicated \nand robust volume ignition.",
"URL": "http://ui.adsabs.harvard.edu/abs/1999LPB....17..209H/abstract",
"title": "Improved use of big laser systems for inertial fusion energy",
"year_published": 1999,
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"Aerospace engineering",
"Inertial frame of reference",
"Fusion power",
"Laser"
],
"first_author": "Heinrich Hora",
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"abstract": "High-power millimeter wave sources are a key enabling technology in fusion energy research. The present state of the art of application of these sources to the areas of heating, current generation, and scattering for diagnostic purposes in fusion plasmas is reviewed. The extrapolation of these applications to future devices and the requirements which they place on sources and transmission lines are also discussed.",
"URL": "https://ieeexplore.ieee.org/document/1158303",
"title": "Applications of high-power millimeter waves in fusion energy research",
"year_published": 2002,
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"Electrical engineering",
"Extrapolation",
"Electric power transmission",
"Aerospace engineering",
"Magnetic confinement fusion",
"Scattering",
"Fusion power",
"Computer science",
"Extremely high frequency",
"Thermonuclear fusion"
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"first_author": "T.C. Luce",
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"abstract": "Physicists at the $3.5bn National Ignition Facility in the US have performed a fusion shot that generated more energy from a controlled nuclear fusion reaction than was needed to power the reaction.",
"URL": "NaN",
"title": "National Ignition Facility demonstrates net fusion energy gain",
"year_published": 2023,
"fields_of_study": [
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"Ignition system",
"Nuclear engineering",
"Nuclear fusion",
"Fusion",
"Fusion power",
"Net (polyhedron)",
"Environmental science",
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"abstract": "This paper reviews the different challenges that are encountered in the delivery of high power lasers as drivers for fusion energy. We will focus on diode-pumped solid-state lasers and we will highlight some of the main recent achievements when using ytterbium, cryogenic cooling and ceramic gain media. Apart from some existing fusion facilities and some military applications of diode-pumped solid-state lasers, we will show that diode-pumped solid-state lasers are scalable to inertial fusion energy (IFE)\u2019s facility level and that the all-fiber laser scheme is very promising.",
"URL": "https://www.cambridge.org/core/journals/high-power-laser-science-and-engineering/article/div-classtitlechallenges-of-high-power-diode-pumped-lasers-for-fusion-energydiv/010957EAB623E1CE7CD0BAE2143A6E2A",
"title": "Challenges of high power diode-pumped lasers for fusion energy",
"year_published": 2014,
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"Power diode",
"High power lasers",
"Computer science",
"Optoelectronics",
"Laser",
"Ytterbium",
"Engineering physics"
],
"first_author": "Bruno Le Garrec",
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"abstract": "Silicon carbide composites are attractive for structural applications in fusion energy systems because of their low activation and afterheat properties, excellent high-temperature properties, corrosion resistance and low density. Another attractive property includes the potential to engineer their properties by location within a component or system to meet variable performance requirements. This can be accomplished by tailoring the fiber type, volume fraction and architecture by location within the component. Also \u03b2 SiC exhibits very low swelling (< 0.2%) over the temperature range of 800 to 1000\u00b0C.These composites are relatively new materials with a limited data base; however, there is sufficient understanding of their performance to identify key issues in their application. These issues include: mechanical, chemical and radiation stability, nuclear transmutation, hermetic behavior, thermal conductivity, mechanical and thermal fatigue, thermal shock, joining and design methodology. Progress is being made...",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST96-A11963062",
"title": "SiC/SiC Composites for Structural Applications in Fusion Energy Systems",
"year_published": 1996,
"fields_of_study": [
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"Composite material",
"Thermal shock",
"Materials science",
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"Fusion power",
"Silicon carbide",
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"abstract": "An emerging industry of nuclear-fusion firms promises to have commercial reactors ready in the next decade.",
"URL": "https://www.ncbi.nlm.nih.gov/pubmed/34789909",
"title": "The start-ups chasing clean, carbon-free fusion energy.",
"year_published": 2021,
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"Energy (signal processing)",
"Renewable energy",
"Fusion power",
"Start up",
"Environmental science",
"Applied physics",
"Carbon"
],
"first_author": "Philip Ball",
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"abstract": "The Z-pinch fusion energy power plant concept [1] is based upon an X-ray driven inertial confinement fusion (ICF) capsule having a hypothetical yield of 3 GJ with an overall target gain in the range of 50-100. In the present paper, a combination of analytic arguments, results of radiation-hydrodynamic computational simulations, and empirical scalings from Z-pinch hohlraum experiments are used to demonstrate that the absorption of approximately 6 MJ of X-ray energy by the capsule and 26 MJ by the hohlraum walls of an ICF target (\u223c 32 MJ total X-ray input) will be adequate to provide a 3 GJ yield. As a result, it appears that the Ref. 1 assumption of a 3 GJ thermonuclear yield with an overall target gain approaching 100 is conceptually feasible.",
"URL": "http://www.osti.gov/scitech/biblio/20854063-target-physics-scaling-pinch-inertial-fusion-energy",
"title": "Target Physics Scaling for Z-Pinch Inertial Fusion Energy",
"year_published": 2005,
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"abstract": "AbstractThe HYLIFE-II inertial fusion power plant design study uses a liquid fall, in the form of jets, to protect the first structural wall from neutron damage, x rays, and blast to provide a 30-y lifetime. HYLIFE-I used liquid lithium. HYLIFE-II avoids the fire hazard of lithium by using a molten salt composed of fluorine, lithium, and beryllium (Li2BeF4) called Flibe. Access for heavy-ion beams is provided. Calculations for assumed heavy-ion beam performance show a nominal gain of 70 at 5 MJ producing 350 MJ, about 5.2 times less yield than the 1.8 GJ from a driver energy of 4.5 MJ with gain of 400 for HYLIFE-I. The nominal 1 GWe of power can be maintained by increasing the repetition rate by a factor of about 5.2, from 1.5 to 8 Hz. A higher repetition rate requires faster re-establishment of the jets after a shot, which can be accomplished in part by decreasing the jet fall height and increasing the jet flow velocity. In addition, although not adequately considered for FIYLIFE-I, there is liquid splas...",
"URL": "https://ui.adsabs.harvard.edu/abs/1992tfe..meetR...7M/abstract",
"title": "Hylife-II Inertial Fusion Energy Power Plant Design",
"year_published": 1992,
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"abstract": "Fusion could be a part of future decarbonized electricity systems, but it will need to compete with other technologies. In particular, pulsed tokamak plants have a unique operational mode, and evaluating which characteristics make them economically competitive can help select between design pathways. Using a capacity expansion and operations model, we determined cost thresholds for pulsed tokamaks to reach a range of penetration levels in a future decarbonized US Eastern Interconnection. The required capital cost to reach a fusion capacity of 100 GW varied from $2,700 to $7,500 kW\u22121, and the equilibrium penetration increases rapidly with decreasing cost. The value per unit power capacity depends on the variable operational cost and on the cost of its competition, particularly fission, much more than on the pulse cycle parameters. These findings can therefore provide initial cost targets for fusion more generally in the United States.",
"URL": "https://arxiv.org/pdf/2209.09373",
"title": "The value of fusion energy to a decarbonized United States electric grid",
"year_published": 2023,
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"abstract": "A report from the US National Academies of Sciences, Engineering, and Medicine calls for a US pilot fusion-energy plant. A report from the US National Academies of Sciences, Engineering, and Medicine calls for a US pilot fusion-energy plant.",
"URL": "https://www.nature.com/articles/d41586-018-07789-w",
"title": "US science academies urge expansion of fusion-energy research",
"year_published": 2018,
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"abstract": "A startup chasing the dream of plentiful, safe, carbon-free electricity from fusion, the energy source of the Sun, has settled on its key technology, a timetable, and now a site for building its compact, affordable reactor. Flush with more than $200 million from investors, including Bill Gates9s Breakthrough Energy, 3-year old Commonwealth Fusion Systems announced last week that later this year it will start to build its first test reactor, dubbed SPARC, in a new facility in Devens, Massachusetts, not far from its current base in Cambridge. The company says the reactor, which would be the first in the world to produce more energy than is needed to run the reaction, could fire up as soon as 2025. Commonwealth and a rival U.K. company have also chosen the technology they think will let them leap ahead of the giant, publicly funded ITER reactor under construction in France and ever further ahead of a U.S. pilot plant being considered by the Department of Energy: small but powerful magnets, made from high-temperature superconductors.",
"URL": "https://ui.adsabs.harvard.edu/abs/2021Sci...371.1091C/abstract",
"title": "Magnet tests kick off bid for net fusion energy",
"year_published": 2021,
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"abstract": "The current energy model, which is based largely on the use of fossil fuels and has a direct influence on global warming and climate change, presents serious problems of unsustainability in the long term [...]",
"URL": "https://www.mdpi.com/1996-1073/17/6/1413/pdf?version=1710474869",
"title": "Editorial: Advances in Nuclear Fusion Energy and Cross-Cutting Technologies",
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"URL": "https://physicstoday.scitation.org/doi/pdf/10.1063/PT.3.3994",
"title": "Will doubling magnetic field strength halve the time to fusion energy",
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"abstract": "We are carrying out a multidisciplinary multi-institutional program to develop the scientific and technical basis for inertial fusion energy (IFE) based on laser drivers and direct-drive targets. The key components are developed as an integrated system, linking the science, technology, and final application of a 1000-MWe pure-fusion power plant. The science and technologies developed here are flexible enough to be applied to other size systems. The scientific justification for this work is a family of target designs (simulations) that show that direct drive has the potential to provide the high gains needed for a pure-fusion power plant. Two competing lasers are under development: the diode-pumped solid-state laser (DPPSL) and the electron-beam-pumped krypton fluoride (KrF) gas laser. This paper will present the current state of the art in the target designs and lasers, as well as the other IFE technologies required for energy, including final optics (grazing incidence and dielectrics), chambers, and target fabrication, injection, and tracking technologies. All of these are applicable to both laser systems and to other laser IFE-based concepts. However, in some of the higher performance target designs, the DPPSL will require more energy to reach the same yield as with the KrF laser.",
"URL": "http://compmat.johnshopkins.edu/files/publications/Science_Technologies_Fusion_Energys.pdf",
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"abstract": "Abstract The US Department of Energy is proposing to construct the National Ignition Facility (NIF) to embark on a program to achieve ignition and modest gain in the laboratory early in the next century. The NIF will use a \u2a7e 1.8 MJ, 0.35 \u03bcm laser with 192 independent beams, a 50-fold increase over the energy of the Nova laser. System performance analyses suggest yields as great as 20 MJ may be achievable. NIF will conduct more than 600 shots per year. The benefits of a micro-fusion capability in the laboratory include essential contributions to defence programs, resolution of important Inertial Fusion Energy (IFE) issues and unparalleled conditions of energy density for basic science and technology research. A start has been made to consider the role the NIF will fill in the development of IFE. While the achievement of ignition and gain speaks for itself in terms of its impact on developing IFE, it is believed there are areas of IFE development, such as fusion power technology, IFE target design and fabrication and understanding chamber dynamics, that would significantly benefit from NIF experiments. In the area of IFE target physics, ion targets will be designed using the NIF laser and the feasibility of high-gain targets will be confirmed. Target chamber dynamics experiments will benefit from X-ray and debris energies that mimic the spatial distribution of neutron heating, activation and tritium breeding in relevant materials. IFE target systems will benefit from evaluating low-cost target fabrication techniques by testing such targets on NIF. Additionally, it is believed that it is feasible to inject up to four targets and engage them with the NIF laser by triggering the beams in groups of ca. 50 separated in time by ca. 0.1 s. Sub-ignition neutron yields would allow an indication of symmetry achieved in such proof-of-principle rep-rate experiments. NIF will be a unique source of data to benchmark predictive capabilities to support affordable IFE technology selections. The total of NIF-IFE experiments may involve several thousands of shots. NIF may support design \u201ccertification\u201d for the follow-on facility to NIF, dedicated to IFE, called the Engineering Test Facility.",
"URL": "https://www.sciencedirect.com/science/article/abs/pii/092037969580000N",
"title": "Contributions of the National Ignition Facility to the development of inertial fusion energy",
"year_published": 1995,
"fields_of_study": [
"Inertial confinement fusion",
"Nuclear engineering",
"Ignition system",
"Fusion power",
"National Ignition Facility",
"Safeguard",
"Energy density",
"Technology research",
"Support design"
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"first_author": "Michael T. Tobin",
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"abstract": "Recent progress(1) in plasma science of the Spherical Tokamak (or Spherical Torus, ST)(2) has indicated relatively robust plasma conditions in a broad number of topical area including strong shaping, stability limits, energy confinement, self-driven current, and sustainment. This progress has enabled an extensive update of the plasma science and fusion engineering conditions of a Component Test Facility (CTF)(3), which is potentially a necessary step in the development of practical fusion energy. The chamber systems testing conditions in a CTF are characterized by high fusion neutron fluxes n > 4.4 1013 n/s/cm2, over sizescale > 105 cm2 and depth-scale > 50 cm, delivering > 3 accumulated displacement per atom (dpa) per year(4). Such chamber conditions are calculated to be achievable in a CTF with R0 = 1.2 m, A = 1.5, elongation ~ 3, Ip ~ 9 MA, BT ~ 2.5 T, producing a driven fusion burn using 36 MW of combined neutral beam and RF power. The ST CTF will test the life time of single-turn, copper alloy center leg for the toroidal field coil without an induction solenoid and neutron shielding, and require physics data on solenoid-free plasma current initiation, ramp-up, and sustainment to multiple MA level. A newmore\u00a0\u00bb systems code that combines the key required plasma and engineering science conditions of CTF has been prepared and utilized as part of this study. The results show high potential for a family of relatively low cost CTF devices to suit a range of fusion engineering science test missions.\u00ab\u00a0less",
"URL": "http://ui.adsabs.harvard.edu/abs/2005IJTFM.125..857P/abstract",
"title": "Spherical Tokamak Plasma Science and Fusion Energy Component Testing",
"year_published": 2005,
"fields_of_study": [
"Nuclear engineering",
"Fusion",
"Magnetic confinement fusion",
"Atomic physics",
"Solenoid",
"Materials science",
"Fusion power",
"Spherical tokamak",
"Neutron radiation",
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"first_author": "Y. K. M. Peng",
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"abstract": "This paper reports on values of fusion energy multiplication [gt]1 which have been shown to be possible during energetic deuterium injection into high-electron-temperature (T[sub e] [gt] 3 keV), quasi-neutral tritium plasmas. The high-temperature requirement is eliminated when a nonneutral plasma is the beam's target. Fusion energy multiplication factors [gt]1 can be obtained in a low-temperature ([lt] 100 eV), nonneutral tritium plasma.",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST92-A30097",
"title": "Fusion Energy Production during Ion Injection into a Nonneutral Plasma",
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"abstract": "This is the final report of a panel set up by the U.S. Department of Energy (DOE) Fusion Energy Sciences Advisory Committee (FESAC) in response to a charge letter from Dr. Ray Orbach (Appendix A). In that letter, Dr. Orbach asked FESAC for \u201can assessment of the present status of\u201d inertial fusion energy (IFE) research carried out in contributing programs. These programs include the heavy ion (HI) beam, the high average power laser (HAPL), and Z-Pinch drivers and associated technologies, including fast ignition (FI). This report, presented to FESAC on March 29, 2004, and subsequently approved by them (Appendix B), presents FESAC's response to that charge.",
"URL": "https://ui.adsabs.harvard.edu/abs/2003JFuE...22...93L/abstract",
"title": "A Review of the U.S. Department of Energy's Inertial Fusion Energy Program",
"year_published": 2003,
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"abstract": "Inertial fusion energy (IFE) reactors require shells with a high-Z coating that is both permeable, for timely filling with deuterium-tritium, and reflective, for survival in the chamber. Previously, gold was deposited on shells while they were agitated to obtain uniform, reproducible coatings. However, these coatings were rather impermeable, resulting in unacceptably long fill times. We report here on an initial study on Pd coatings on shells in the same manner. We have found that these palladium-coated shells are substantially more permeable than gold. Pd coatings on shells remained stable on exposure to deuterium. Pd coatings had lower reflectivity compared to gold that leads to a lower working temperature, and efficiency, of the proposed fusion reactor. Seeking to combine the permeability of Pd coatings and high reflectivity of gold, AuPd-alloy coatings were produced using a cosputtering technique. These alloys demonstrated higher permeability than Au and higher reflectivity than Pd. However, these coatings were still less reflective than the gold coatings. To improve the permeability of gold's coatings, permeation experiments were performed at higher temperatures. With the parameters of composition, thickness, and temperature, we have the ability to comply with a large target design window.",
"URL": "https://www.ans.org/pubs/journals/fst/a_277",
"title": "Optimizing High-Z Coatings for Inertial Fusion Energy Shells",
"year_published": 2003,
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"first_author": "Elizabeth H. Stephens",
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"abstract": "The use of thin membranes to suspend an inertial fusion energy fuel capsule in a holder or hohlraum for injection into a reaction chamber is investigated. Also discussed is the stress that occurs in the fuel within a capsule during acceleration. To determine the maximum target acceleration, capsule displacement and membrane deformation angle are calculated for an axisymmetric geometry for a range of membrane strain and capsule size. Membranes must be thin (perhaps <1 {mu}m) to minimize their effect on capsule implosion symmetry. Typical target injection scenarios prefer accelerations in excess of 1000 m/s{sup 2}. Acceleration in excess of 1600 m/s{sup 2} for a 2.4-mm-radius 30-mg capsule is possible with two 0.1-{mu}m-thick membranes. Added stress from vibrations could cause a factor of 2 decrease in the allowed acceleration unless the acceleration profile is modified to mitigate this effect. However, if the acceleration is gradually increased and then decreased, over a few membrane oscillation periods (i.e., a few milliseconds), the membrane stress due to oscillation overshoot and the final capsule oscillation amplitude is minimal. Compared with a single membrane, a dual membrane geometry allows several times greater acceleration with reduced capsule displacement. 7 refs., 14 figs., 1 tab.",
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"title": "Membrane support of accelerated fuel capsules for inertial fusion energy",
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"abstract": "This paper describes a methodology based on decision analysis for addressing major program decisions in the development of magnetic fusion energy. The development of this complex technology involves a sequence of funding choices over time among multiple technical approaches and under considerable performance uncertainty. The methodology focuses on the next major facility decision in the U.S magnetic fusion energy program. The decision alternatives include the construction and testing of a major experimental facility based on one of two leading technical approaches (reactor designs), an accelerated program where both approaches are pursued, or delaying another facility until more information is available. Subsequent decisions depend on the first decision and its outcome and involve either further development of the best technical approach or abandonment of the entire research and development program. Analysis of a particular sequence of program decisions takes account of the uncertainties in the ultimate e...",
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"abstract": "With corporate participation, researchers seek to build a pilot fusion-energy plant within 15 years. With corporate participation, researchers seek to build a pilot fusion energy plant within 15 years.",
"URL": "https://europepmc.org/article/MED/29542724",
"title": "MIT launches multimillion-dollar collaboration to develop fusion energy",
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"abstract": "A zero-dimensional model that describes the evolution of plasma and gas parameters during the afterglow phase of cyclic operation of an inertial fusion energy chamber is developed. The afterglow phase determines the conditions for next fuel-target injection and therefore its thorough analysis is very important for conceptual design of inertial fusion power plants. The model incorporates important effects of intrinsic impurity ion radiation on plasma cooling as well as of chamber opacity with respect to resonance radiation on plasma recombination in the working chamber. The decay times for the plasma and gas energy and, in particular, their dependence on initially stored energy, chamber size, and background gas concentration are analyzed. The heat power load onto the cryogenic fuel target due to residual plasma, gas, and radiation field is calculated. It is found that the higher the background gas density, the longer is the time into the afterglow phase necessary to reduce the heat flux on the target to an acceptable level.",
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"abstract": "Abstract This paper provides an overview of one option for LLNL's LIFE power plant design with a focus on the fusion nuclear science and technology aspects. The design is based on 132\u00a0MJ yield indirect-drive targets ignited by a diode pumped solid state laser that delivers 2.2\u00a0MJ on target at a pulse rate of 8.3\u00a0Hz for the first market entry plant (MEP) and 16.7\u00a0Hz for subsequent first generation commercial plants (FCP). The chamber first wall is steel which is protected from direct exposure to target X-ray and ion emissions by a Xe fill gas at \u223c6\u00a0\u03bcg/cm 3 . Reduced activation ferritic martensitic steel is proposed for the MEP while commercial plants will utilize higher strength, more radiation damage tolerate steels such as ODS, which can also operate at higher temperature for improved thermal efficiency and overall plant economics. Liquid Li is the primary coolant and tritium breeding material. An intermediate loop with molten salt as the working fluid transports power to a Rankine steam cycle; the estimated gross electric power conversion efficiency is 45% for the MEP and 47% for the FCP.",
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"abstract": "Recent target injection and tracking experimental results with simulated room-temperature indirect-drive targets are briefly discussed. Extensions of those experiments for improved timing accuracy ...",
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"abstract": "A comprehensive conceptual design for a diode pumped solid state laser (DPSSL) as a driver for an inertial fusion energy (IFE) power plant is presented. This design is based on recent technical advances that offer potential solutions to difficulties previously associated with the use of a laser for IFE applications. The design was selected by using a systems analysis code that optimizes a DPSSL configuration by minimizing the calculated cost of electricity (COE). The code contains the significant physics relevant to the DPSSL driver, but treats the target chamber and balance of plant costs generically using scaling relations published for the Sombrero KrF laser concept. The authors describe the physics incorporated in the code, predict DPSSL performance and its variations with changes in the major parameters, discuss IFE economics and technical risk, and identify the high leverage development efforts that can make DPSSL driven IFE plants more economically competitive. It is believed that this study is a significant advance over previous conceptual studies of DPSSLs for IFE because it incorporates a new cost effective gain medium, applies a potential solution to the `final optics` problem, and considers the laser physics in substantially greater detail. The result is the introduction of an option for an IFE driver that has relatively low development costs and that builds upon the mature laser technology base already developed for Nova and being developed for the proposed National Ignition Facility. The baseline design of the paper has a product of laser efficiency and target gain of \u03b7G~6.6 and a COE of 8.6 cents/kW.h for a 1 GW(e) plant with a target gain of 76 at 3.7 MJ. Higher \u03b7G(11) and lower COEs (6.6 cents/kW.h) can be achieved with target gains twice as high",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/36/1/I06/meta",
"title": "A diode pumped solid state laser driver for inertial fusion energy",
"year_published": 1996,
"fields_of_study": [
"Inertial confinement fusion",
"Conceptual design",
"Nova (laser)",
"Diode-pumped solid-state laser",
"Automotive engineering",
"National Ignition Facility",
"Mercury laser",
"Active laser medium",
"Cost of electricity by source"
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"first_author": "Charles D. Orth",
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"abstract": "The use of swirling annular vortex flow inside beam entrance tubes can protect beam-line structural materials in chambers for heavy-ion inertial fusion energy (IFE) applications. An annular wall jet, or vortex tube, is generated by injecting liquid tangent to the inner surface of a tube wall with both axially and azimuthally directed velocity components. A layer of liquid then lines the beam tube wall, which may improve the effectiveness of neutron shielding, and condenses and removes vaporized coolant that may enter the beam tubes. Vortex tubes have been constructed and tested with a thickness of three-tenths the pipe radius. Analysis ofthe flow is given, along with experimental examples of vortex tube fluid mechanics and an estimate of the layer thickness, based on simple mass conservation considerations.",
"URL": "https://www.ans.org/pubs/journals/fst/a_281",
"title": "Annular Vortex Generation for Inertial Fusion Energy Beam-Line Protection",
"year_published": 2003,
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"Jet (fluid)",
"Optics",
"Physics",
"Vortex",
"Vortex ring",
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"abstract": "We present the results of performance modeling of a diode-pumped solid-state HiLASE laser designed for use in inertial fusion energy power plants. The main amplifier concept is based on a He-gas-cooled multi-slab architecture similar to that employed in Mercury laser system. Our modeling quantifies the reduction of thermally induced phase aberrations and average depolarization in :YAG slabs by a combination of helium cryogenic cooling and properly designed (doping/width) cladding materials.",
"URL": "https://www.cambridge.org/core/services/aop-cambridge-core/content/view/FE7AFAED3A33CA4680A1601A78D30CC1/S2095471914000152a.pdf/div-class-title-design-of-a-kj-class-hilase-laser-as-a-driver-for-inertial-fusion-energy-div.pdf",
"title": "Design of a kJ-class HiLASE laser as a driver for inertial fusion energy",
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"Birefringence",
"Materials science",
"Amplifier",
"Fusion power",
"Mercury laser",
"Laser",
"Helium",
"Cladding (fiber optics)",
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"first_author": "Antonio Lucianetti",
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"abstract": "Fuelling of a commercial inertial fusion energy (IFE) power plant consists of supplying about 500\u00a0000 fusion targets each day. The most challenging type of target in this regard is that for laser driven direct drive IFE power plants. Spherical capsules with cryogenic DT fuel must be injected into the centre of a reaction chamber operating at temperatures as high as 1500\u00b0 C and possibly containing as much as 0.5\u00a0torr of xenon fill gas. The DT layer must remain highly symmetric, have a smooth inner ice surface finish and reach the chamber centre (CC) at a temperature of about 18.5\u00a0K. This target must be positioned at the centre of the chamber with a placement accuracy of \u00b15\u00a0mm. The accuracy of alignment of the laser driver beams and the target in its final position must be within \u00b120\u00a0\u03bcm. All this must be repeated six times per second. The method proposed to meet these requirements is to inject the targets into the reaction chamber at high speed ( \u2248 400\u00a0m/s), track them, and hit them in flight with steerable driver beams. The challenging scientific and technological issues associated with this task are being addressed through a combination of analyses, modelling, materials property measurements and demonstration tests with representative injection equipment. Measurements of relevant DT properties are planned at Los Alamos National Laboratory. An experimental target injection and tracking system is now being designed to support the development of survivable targets and demonstrate successful injection scenarios. Analyses of target heating are under way. Calculations have shown that a direct drive target must have a highly reflective outer surface to prevent excess heating by thermal radiation. In addition, heating by hot chamber fill gas during injection far outweighs that by the thermal radiation. It is concluded that the dry wall, gas filled reaction chambers must have gas pressures and wall temperatures less than previously assumed in order to prevent excessive heating in current direct drive target designs. An integrated power plant systems study to address this issue has been initiated.",
"URL": "http://ui.adsabs.harvard.edu/abs/2001NucFu..41..527G/abstract",
"title": "Developing target injection and tracking for inertial fusion energy power plants",
"year_published": 2001,
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"Current (fluid)",
"Tracking system",
"Power (physics)",
"Materials science",
"Fusion power",
"Tracking (particle physics)",
"Power station",
"Laser",
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"first_author": "D. T. Goodin",
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"abstract": "The speed at which fusion energy can be deployed is considered. Several economical factors are identified that impede this speed. Most importantly, the combination of an unprecedentedly high investment level needed for the proof of principle and the relatively long construction time of fusion plants precludes an effective innovation cycle. The valley of death is discussed, i.e. the period when a large investment is needed for the construction of early generations of fusion reactors, when there is no return yet. It is concluded that, within the mainstream scenario-a few DEMO reactors towards 2060 followed by generations of relatively large reactors-there is no realistic path to an appreciable contribution to the energy mix in the twenty-first century if economic constraints are applied. In other words, fusion will not contribute to the energy transition in the time frame of the Paris climate agreement. Within the frame of this analysis, the development of smaller, cheaper and most importantly, fast-to-build fusion plants could possibly represent an option to accelerate the introduction of fusion power. Whether this is possible is a technical question that is outside the scope of this paper, but this question is addressed in other contributions to the Royal Society workshop. This article is part of a discussion meeting issue 'Fusion energy using tokamaks: can development be accelerated?'.",
"URL": "https://pure.tue.nl/ws/files/123942756/RS.LopesCardozo.FutureofFusion.lastauthorversion_2_.pdf",
"title": "Economic aspects of the deployment of fusion energy: the valley of death and the innovation cycle.",
"year_published": 2019,
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"Proof of concept",
"Economics",
"Fusion power",
"Investment (macroeconomics)",
"Energy mix",
"Energy transition",
"Scope (project management)",
"Industrial organization",
"Nuclear fusion"
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"first_author": "N.J. Lopes Cardozo",
"scholarly_citations_count": 12,
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{
"abstract": "The 3 kJ UNU/ICTP Plasma Focus Facility is the most significant device associated with the AAAPT (Asian African Association for Plasma Training). In original and modified/upgraded form it has trained generations of plasma focus (PF) researchers internationally, producing many PhD theses and peer-reviewed papers. The Lee Model code was developed for the design of this PF. This code has evolved to cover all PF machines for design, interpretation and optimization, for derivation of radiation scaling laws; and to provide insights into yield scaling limitations, radiative collapse, speed-enhanced and current-stepped PF variants. As example of fresh perspectives derivable from this code, this paper presents new results on energy transfers of the axial and radial phases of generalized PF devices. As the world moves inexorably towards the Fusion Energy Age it becomes ever more important to train plasma fusion researchers. A recent workshop in Nepal shows that demand for such training continues. Even commercial pr...",
"URL": "https://www.worldscientific.com/doi/pdf/10.1142/S2010194514603135",
"title": "Developing a plasma focus research training system for the fusion energy age",
"year_published": 2014,
"fields_of_study": [
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"Engineering",
"Industrial engineering",
"Code (cryptography)",
"Fusion power",
"Training system",
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"abstract": "Abstract The availability of fusion energy could prove valuable in meeting carbon mitigation targets over the course of the century. We use recent cost estimates for future fusion power plants in order to incorporate fusion into the Global Change Assessment Model (GCAM), a long-term energy and environment model used to study the interaction between technology, climate, and public policy. Results show that fusion's growth will depend on: the chosen carbon mitigation target (if any); the availability of competing carbon-neutral options for the provision of baseload electrical power, in particular nuclear fission as well as carbon capture and storage; the chosen discount rate; the initial year of availability; and the assumed costs of fusion electricity. We quantify the present value of the fusion option while varying the assumptions about these other parameters, and we find that it is, in general for our range of assumptions, significantly larger than the estimated cost of a comprehensive R&D plan to develop fusion energy. The results emphasize the wisdom in hedging against uncertainty in future technology availability by pursuing the development of multiple options that could feasibly play a major role in the latter half of the century.",
"URL": "https://econpapers.repec.org/article/eeeeneeco/v_3a51_3ay_3a2015_3ai_3ac_3ap_3a346-353.htm",
"title": "Investigating the value of fusion energy using the Global Change Assessment Model",
"year_published": 2015,
"fields_of_study": [
"Environmental resource management",
"Base load power plant",
"Environmental economics",
"Technological change",
"Electricity",
"Carbon capture and storage",
"Fusion power",
"Electric power",
"Computer science",
"Present value",
"Cost estimate"
],
"first_author": "David Turnbull",
"scholarly_citations_count": 5,
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"abstract": "The National Ignition Facility (NIF), the world's largest and most powerful laser system for inertial confinement fusion (ICF) and experiments studying high-energy-density (HED) science, is nearing completion at Lawrence Livermore National Laboratory (LLNL). NIF, a 192-beam Nd-glass laser facility, will produce 1.8 MJ, 500 TW of light at the third-harmonic, ultraviolet light of 351 nm. The NIF project is scheduled for completion in March 2009. Currently, all 192 beams have been operationally qualified and have produced over 4.0 MJ of light at the fundamental wavelength of 1053 nm, making NIF the world's first megajoule laser. The principal goal of NIF is to achieve ignition of a deuterium\u2013tritium (DT) fuel capsule and provide access to HED physics regimes needed for experiments related to national security, fusion energy and for broader scientific applications.The plan is to begin 96-beam symmetric indirect-drive ICF experiments early in FY2009. These first experiments represent the next phase of the National Ignition Campaign (NIC). This national effort to achieve fusion ignition is coordinated through a detailed plan that includes the science, technology and equipment such as diagnostics, cryogenic target manipulator and user optics required for ignition experiments. Participants in this effort include LLNL, General Atomics, Los Alamos National Laboratory, Sandia National Laboratory and the University of Rochester Laboratory for Energetics (LLE). The primary goal for NIC is to have all of the equipment operational and integrated into the facility soon after project completion and to conduct a credible ignition campaign in 2010. When the NIF is complete, the long-sought goal of achieving self-sustaining nuclear fusion and energy gain in the laboratory will be much closer to realization.Successful demonstration of ignition and net energy gain on NIF will be a major step towards demonstrating the feasibility of inertial fusion energy (IFE) and will likely focus the world's attention on the possibility of an ICF energy option. NIF experiments to demonstrate ignition and gain will use central-hot-spot (CHS) ignition, where a spherical fuel capsule is simultaneously compressed and ignited. The scientific basis for CHS has been intensively developed (Lindl 1998 Inertial Confinement Fusion: the Quest for Ignition and Energy Gain Using Indirect Drive (New York: American Institute of Physics)) and has a high probability of success. Achieving ignition with CHS will open the door for other advanced concepts, such as the use of high-yield pulses of visible wavelength rather than ultraviolet and fast ignition concepts (Tabak et al 1994 Phys. Plasmas 1 1626\u201334, Tabak et al 2005 Phys. Plasmas 12 057305). Moreover, NIF will have important scientific applications in such diverse fields as astrophysics, nuclear physics and materials science.This paper summarizes the design, performance and status of NIF, experimental plans for NIC, and will present laser inertial confinement fusion\u2013fission energy (LIFE) as a path to achieve carbon-free sustainable energy.",
"URL": "https://www.osti.gov/servlets/purl/1130032",
"title": "Ignition on the National Ignition Facility: a path towards inertial fusion energy",
"year_published": 2009,
"fields_of_study": [
"Inertial confinement fusion",
"Nuclear engineering",
"Fusion ignition",
"Nova (laser)",
"Ignition system",
"Nuclear physics",
"Fusion power",
"National Ignition Facility",
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"Nuclear fusion"
],
"first_author": "Edward I. Moses",
"scholarly_citations_count": 156,
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"abstract": "The paper discusses edge stability, beta limits and power handling issues for negative triangularity tokamaks. The edge magnetohydrodynamic stability is the most crucial item for power handling. For the case of negative triangularity the edge stability picture is quite different from that for conventional positive triangularity tokamaks: the second stability access is closed for localized Mercier/ballooning modes due to the absence of a magnetic well, and nearly internal kink modes set the pedestal height limit to be weakly sensitive to diamagnetic stabilization just above the margin of the localized mode Mercier criterion violation. While a negative triangularity tokamak is thought to have a low beta limit with its magnetic hill property, it is found that plasmas with reactor-relevant values of normalized beta beta(N) > 3 can be stable to global kink modes without wall stabilization with appropriate core pressure profile optimization against localized mode stability, and also with increased magnetic shear in the outer half-radius. The beta limit is set by the n = 1 mode for the resulting flat pressure profile. The wall stabilization is very inefficient due to strong coupling between external and internal modes. The n > 1 modes are increasingly internal when approaching the localized mode limit, and set a lower beta in the case of the peaked pressure profile leading to a Mercier unstable core. With the theoretical predictions supported by experiments, a negative triangularity tokamak would become a prospective fusion energy system with other advantages including a larger separatrix wetted area, more flexible divertor configuration design, wider trapped particle-free scrape-off layer, lower background magnetic field for internal poloidal field coils, and larger pumping conductance from the divertor room.",
"URL": "http://ui.adsabs.harvard.edu/abs/2015NucFu..55f3013M/abstract",
"title": "The negative triangularity tokamak: stability limits and prospects as a fusion energy system",
"year_published": 2015,
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"Physics",
"Atomic physics",
"Fusion power",
"Divertor",
"Pedestal",
"Beta (plasma physics)",
"Mechanics",
"Plasma",
"Diamagnetism"
],
"first_author": "S. Yu. Medvedev",
"scholarly_citations_count": 57,
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"abstract": "We proposed a novel laser amplifier for inertial fusion energy (IFE) based on an edge-pumped, gas-cooled multi-slab architecture. Compared to the face-pumped laser amplifiers for IFE, this architecture enables the pump, coolant and laser propagating orthogonally in the amplifier, thereby decoupling them in space and being beneficial to construction of the amplifier. To satisfy the high efficiency required for IFE, high-irradiance rectangle-waveguide coupled diode laser arrays are employed in the edge-pumped architecture and the pump light will be homogenized by total internal reflection. A traverse gradient doping profile is applied to the gain media, thus the pump absorption and gain uniformity can be separately optimized. Furthermore, the laser beam normal to the surfaces of the gas-cooled slabs will experience minimum thermal wavefront distortions in the amplifier head and ensure high beam quality. Since each slab has its own pump source and uniform gain in the aperture, power scaling can be easily achieved by placing identical slabs along the laser beam axis. Our investigations might provide an efficient and convenient way to design and optimize the amplifiers for IFE.",
"URL": "http://ui.adsabs.harvard.edu/abs/2016SPIE10016E..0FL/abstract",
"title": "Edge-pumped multi-slab amplifier for inertial fusion energy (IFE)",
"year_published": 2016,
"fields_of_study": [
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"Optics",
"Semiconductor laser theory",
"Wavefront",
"Aperture",
"Materials science",
"Amplifier",
"Laser power scaling",
"Fusion power",
"Laser"
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"first_author": "Min Li",
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"sentence": "To satisfy the high efficiency required for IFE, high-irradiance rectangle-waveguide coupled diode laser arrays are employed in the edge-pumped architecture and the pump light will be homogenized by total internal reflection.",
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"category": "Nuclear Fusion Technique",
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"entity": "Rectangle-waveguide coupled diode laser arrays"
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{
"sentence": "A traverse gradient doping profile is applied to the gain media, thus the pump absorption and gain uniformity can be separately optimized.",
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{
"sentence": "Furthermore, the laser beam normal to the surfaces of the gas-cooled slabs will experience minimum thermal wavefront distortions in the amplifier head and ensure high beam quality.",
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"category": "Experimental Apparatus",
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{
"sentence": "Since each slab has its own pump source and uniform gain in the aperture, power scaling can be easily achieved by placing identical slabs along the laser beam axis.",
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"sentence": "Our investigations might provide an efficient and convenient way to design and optimize the amplifiers for IFE.",
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{
"abstract": "The flow of residual metal vapor in an inertial fusion energy (IFE) reactor chamber causes (a) forced convection heat transport to the target, (b) drag force to the target, and (c) deviation of the orbit of the target. To solve these difficulties, a flying metal pipe concept for target transport in an IFE reactor is proposed. The metal pipe is composed of material identical to the liquid metal used in the IFE reactor. The metal pipe (typically 0.5-cm radius and 2-m length) is injected from the top of the IFE reactor chamber. Subsequently, the IFE target is injected, and it goes into the metal pipe, goes out from the other side of the pipe, and arrives at the center of the IFE reactor chamber to be shot by energy beams. The target in the pipe is protected against radiation, forced convection heat from residual gas, and the wind in the IFE reactor chamber. In the case that the flying metal pipe is used in the reactor, heat transport to the target and deviation of the orbit of the target decrease. After microexplosion of the IFE target, the metal pipe arrives at the bottom of the reactor chamber and melts in the liquid-metal pool.",
"URL": "https://www.ans.org/pubs/journals/fst/a_274",
"title": "Flying metal pipe for target transport in inertial fusion energy reactor",
"year_published": 2003,
"fields_of_study": [
"Inertial confinement fusion",
"Convection",
"Nuclear engineering",
"Materials science",
"Forced convection",
"Fusion power",
"Liquid metal",
"Heat transfer",
"Drag",
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],
"first_author": "Ryusuke Tsuji",
"scholarly_citations_count": 2,
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{
"abstract": "The heating of a small particle of deuterium\u2010tritium by laser radiation is considered and conditions for energy gain determined. The size of the D\u2010T particle for a balance of energy input and neutron energy output is computed as a function of initial plasma temperature. The electrical energy required for this breakeven condition is shown and increases as the inverse fourth power of laser efficiency. Because electrons are first heated by the laser radiation and then must transfer their energy to ions by collisions, a computation of electron\u2010ion thermalization is presented. These results show that electron\u2010ion thermalization through collisions applies a severe limitation on most cases for producing net fusion energy and must be considered in a consistent manner for smaller particles.",
"URL": "http://ui.adsabs.harvard.edu/abs/1971JAP....42.1035J/abstract",
"title": "Production of Net Fusion Energy from Laser\u2010Heated Target Plasmas",
"year_published": 1971,
"fields_of_study": [
"Electron",
"Neutron",
"Radiation",
"Atomic physics",
"Chemistry",
"Fusion power",
"Neutron temperature",
"Laser",
"Plasma",
"Electric potential energy"
],
"first_author": "Roy R. Johnson",
"scholarly_citations_count": 9,
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"sentence": "Because electrons are first heated by the laser radiation and then must transfer their energy to ions by collisions, a computation of electronion thermalization is presented.",
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"sentence": "These results show that electronion thermalization through collisions applies a severe limitation on most cases for producing net fusion energy and must be considered in a consistent manner for smaller particles.",
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{
"abstract": "This paper presents our conceptual design for laser drivers used in Laser Inertial Fusion Energy (LIFE) power plants. Although we have used only modest extensions of existing laser technology to en...",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST10-313",
"title": "Compact, Efficient Laser Systems Required for Laser Inertial Fusion Energy",
"year_published": 2011,
"fields_of_study": [
"Conceptual design",
"Aerospace engineering",
"Power (physics)",
"Laser Inertial Fusion Energy",
"Laser technology",
"Computer science",
"Laser"
],
"first_author": "Andy J. Bayramian",
"scholarly_citations_count": 72,
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{
"abstract": "In an inertial fusion energy (IFE) reactor of 1000-MW(electric) fusion power, 95% flibe and 5% fuel with DR{sub c} thickness instead of 100% flibe are used. At startup, the tritium breeding ratio and M-blanket energy multiplication ratio are 1.05 and 1.26 for UF{sub 4} and DR{sub c} [approximately equal to] 60 cm, respectively. These values increase during an operation period of 30 yr. In 11 yr, M increases from 1.26 to 2 [2000 MW(electric)]. After operation of 11 yr, the energy production is stabilized by means of separation of produced plutonium. After 30 yr, displacement per atom (dpa) and helium production in the first wall are calculated as 92 dpa and 590 ppm, respectively. In addition, the cost of electricity values of the HYLIFE-II and the improved HYLIFE-II of 2000 MW(electric) drop from 4.5 and 3.2 cent/kW.h to 4.18 and 3.00 cent/kW.h, respectively. On the other hand, the IFE reactor has the fissile fuel breeding potential of 70 tonnes. The fissile fuel of 45 tonnes corresponding to [approximately equal to]2350 kg/yr would be sufficient to provide makeup fuel for [approximately equal to]10 light water reactors after 11 yr. After the shutdown process, 25 tonnes of fissile fuel with fuel enrichmentmore\u00a0\u00bb of 23% would be left over.\u00ab\u00a0less",
"URL": "https://ans.org/pubs/journals/fst/a_263",
"title": "Improvement of the inertial fusion energy reactor performance by means of UF4 and ThF4",
"year_published": 2003,
"fields_of_study": [
"Inertial confinement fusion",
"Nuclear engineering",
"Nuclear physics",
"Materials science",
"Fusion power",
"Hybrid reactor",
"FLiBe",
"Shutdown",
"Plutonium",
"Tonne",
"Fissile material"
],
"first_author": "Sebahattin \u00dcnalan",
"scholarly_citations_count": 6,
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{
"abstract": "A LIFE laser driver needs to be designed and operated which meets the rigorous requirements of the NIF laser system while operating at high average power, and operate for a lifetime of >30 years. Ignition on NIF will serve to demonstrate laser driver functionality, operation of the Mercury laser system at LLNL demonstrates the ability of a diode-pumped solid-state laser to run at high average power, but the operational lifetime >30 yrs remains to be proven. A Laser Technology test Facility (LTF) has been designed to specifically address this issue. The LTF is a 100-Hz diode-pumped solid-state laser system intended for accelerated testing of the diodes, gain media, optics, frequency converters and final optics, providing system statistics for billion shot class tests. These statistics will be utilized for material and technology development as well as economic and reliability models for LIFE laser drivers.",
"URL": "https://internal.iopscience.iop.org/article/10.1088/1742-6596/244/3/032016",
"title": "A Laser Technology Test Facility for Laser Inertial Fusion Energy (LIFE)",
"year_published": 2010,
"fields_of_study": [
"Inertial confinement fusion",
"Electrical engineering",
"Engineering",
"Ignition system",
"Laser Inertial Fusion Energy",
"Converters",
"Mercury laser",
"Reliability (semiconductor)",
"Laser",
"Diode"
],
"first_author": "Andy J. Bayramian",
"scholarly_citations_count": 12,
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"entity": "frequency converters"
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"sentence": "These statistics will be utilized for material and technology development as well as economic and reliability models for LIFE laser drivers.",
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{
"abstract": "We describe near-term heavy ion fusion (HIF) research objectives associated with developing an inertial fusion energy demonstration power plant. The goal of this near-term research is to lay the essential groundwork for an intermediate research experiment (IRE), designed to demonstrate all the key driver beam manipulations at a meaningful scale, and to enable HIF relevant target physics experiments. This is a very large step in size and complexity compared to HIF experiments to date, and if successful, it would justify proceeding to a demonstration fusion power plant. With an emphasis on accelerator research, this paper is focused on the most important near-term research objectives to justify and to reduce the risks associated with the IRE. The chosen time scale for this research is 5--10 years, to answer key questions associated with the HIF accelerator drivers, in turn enabling a key decision on whether to pursue a much more ambitious and focused inertial fusion energy research and development program. This is consistent with the National Academies of Sciences Review of Inertial Fusion Energy Systems Interim Report, which concludes that ``it would be premature at the present time to choose a particular driver approach\\dots{}'' and encouraged the continued development of community consensus on critical issues, and to develop ``options for a community-based roadmap for the development of inertial fusion as a practical energy source.''",
"URL": "http://ui.adsabs.harvard.edu/abs/2013PhRvS..16b4701S/abstract",
"title": "Research and development toward heavy ion driven inertial fusion energy",
"year_published": 2013,
"fields_of_study": [
"Physics",
"Nanotechnology",
"Inertial frame of reference",
"Key (cryptography)",
"Systems engineering",
"Fusion power",
"Development (topology)",
"Scale (chemistry)",
"Energy source",
"Heavy ion",
"Power station"
],
"first_author": "Peter A. Seidl",
"scholarly_citations_count": 10,
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"abstract": "AbstractThe tokamak approach, utilizing a toroidal magnetic field configuration to confine a hot plasma, is one of the most promising designs for developing reactors that can exploit nuclear fusion to generate electrical energy1,2. To reach the goal of an economical reactor, most tokamak reactor designs3\u201310 simultaneously require reaching a plasma line-averaged\u00a0density above an empirical limit\u2014the so-called Greenwald density11\u2014and attaining an energy confinement quality better than the standard high-confinement mode12,13. However, such an operating regime has never been verified in experiments. In addition, a long-standing challenge in the high-confinement mode has been the compatibility between a high-performance core and avoiding large, transient edge perturbations that can cause very high heat loads on the plasma-facing-components in tokamaks. Here we report the demonstration of stable tokamak plasmas with a line-averaged density approximately 20% above the Greenwald density and an energy confinement quality of approximately 50% better than the standard high-confinement mode, which was realized by taking advantage of the enhanced suppression of turbulent transport granted by high density-gradients in the high-poloidal-beta scenario14,15. Furthermore, our experimental results show an integration of very low edge transient perturbations with the high normalized density and confinement core. The operating regime we report supports some critical requirements in many fusion reactor designs all over the world and opens a potential avenue to an operating point for producing economically attractive fusion energy.",
"URL": "NaN",
"title": "A high-density and high-confinement tokamak plasma regime for fusion energy",
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"abstract": "Motivated by the shock ignition approach to improve the performance of inertial fusion targets, we make a series of studies of the stability of shock waves in planar and converging geometries. We examine stability of shocks moving through distorted material and driving shocks with non-uniform pressure profiles. We then apply a fully 3D perturbation, following this spherically converging shock through collapse to a distorted plane, bounce and reflection into an outgoing perturbed, broadly spherical shock wave. We find broad shock stability even under quite extreme perturbation.",
"URL": "http://www.osti.gov/scitech/biblio/22304446-stability-shocks-relating-shock-ignition-inertial-fusion-energy-scheme",
"title": "Stability of shocks relating to the shock ignition inertial fusion energy scheme",
"year_published": 2014,
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"Ignition system",
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"abstract": "The emission of photons and energetic ions by the burn and subsequent explosion of inertial fusion energy (IFE) targets poses a threat to the survival of the target chambers in future IFE power plants. Immediately after the deposition of target output, the chamber can experience sufficient heating to cause vaporization, melting, and shock loading on chamber walls. Until high-yield targets can be ignited in laboratory experiments, predictions of the nature of the target output and the response of the target chamber must be made with radiation-hydrodynamics computer codes that need to be validated with relevant smaller scale experiments. Physical models of equation of state, opacity, and radiation transport are in special need of validation. Issues of target output and chamber response requiring experiments and computer modeling are discussed and initial results from experiments are presented. Calculations of x ray and debris output from direct-drive IFE targets are shown and sensitivity of the output spect...",
"URL": "https://core.ac.uk/display/5058690",
"title": "Inertial fusion energy target output and chamber response: Calculations and experiments",
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"Vaporization",
"Fusion power",
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"first_author": "Robert R. Peterson",
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"abstract": "Purpose \u2013 The fusion energy research in Europe is developed by a set of laboratories of different countries and organisations. EFDA is an organisation whose main objective is to promote and improve the coordination and collaboration among these laboratories. This paper sets out to describe a working federation (EFDA\u2010Fed) that gathers EFDA (as organisation) and a set of fusion research laboratories: EURATOM/CIEMAT (Spain), CEA (France), JET (UK), IST (Portugal) and KFKI/HAS (Hungary).Design/methodology/approach \u2013 To achieve the objective a federation among all the organisations has been implemented based on PAPI as the authentication and authorization infrastructure that provides a security layer for accessing data among organisations.Findings \u2013 During the implementation of EFDA federation some improvements in distributed single sign on systems have been achieved such as the integration of JAVA applications and a single sign off mechanism.Practical implications \u2013 Users who belong to one of the federated or...",
"URL": "https://www.emerald.com/insight/content/doi/10.1108/10650740810921493/full/html",
"title": "EFDA\u2010fed: European federation among fusion energy research laboratories",
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"Laboratory testing",
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"abstract": "Abstract Full power operation of the International Thermonuclear Experimental Reactor (ITER) has been delayed and will now begin in 2035. Delays to the ITER schedule may affect the availability of tritium for subsequent fusion devices, as the global CANDU-type fission reactor fleet begins to phase out over the coming decades. This study provides an up to date account of future tritium availability by incorporating recent uncertainties over the life extension of the global CANDU fleet, as well as considering the potential impact of tritium demand by other fusion efforts. Despite the delays, our projections suggest that CANDU tritium remains sufficient to support the full operation of ITER. However, whether there is tritium available for a DEMO reactor following ITER is largely uncertain, and is subject to numerous uncontrollable externalities. Further tritium demand may come from any number of private sector \u201ccompact fusion\u201d start-ups which have emerged in recent years, all of which aim to accelerate the development of fusion energy. If the associated technical challenges can be overcome, compact fusion programmes have the opportunity to use tritium over the next two decades whilst it is readily available, and before full power DT operation on ITER starts in 2035. Assuming a similar level of performance is achievable, a compact fusion development programme, using smaller reactors operating at lower fusion power, would require smaller quantities of tritium than the ITER programme, leaving sufficient tritium available for multiple concepts to be developed concurrently. The development of concurrent fusion concepts increases the chances of success, as it spreads the risk of failure. Additionally, if full tritium breeding capability is not expected to be demonstrated in DEMO until after 2050, an opportunity exists for compact fusion programmes to incorporate tritium breeding technology in nearer-term devices. DD start-up, which avoids the need for external tritium for reactor start-up, is dependent upon full tritium breeding capability, and may be essential for large-scale commercial roll-out of fusion energy. As such, from the standpoint of availability and use of external tritium, a compact route to fusion energy may be more advantageous, as it avoids longer-term complications and uncertainties in the future supply of tritium.",
"URL": "https://www.sciencedirect.com/science/article/abs/pii/S092037961830379X",
"title": "Tritium supply and use: a key issue for the development of nuclear fusion energy",
"year_published": 2018,
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"Energy (signal processing)",
"Key (cryptography)",
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"Computer science",
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"abstract": "The proposed Fusion Nuclear Science Facility (FNSF) represents the first facility to enter the complex fusion nuclear regime, and its technical mission and attributes are being developed. The FNSF ...",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST14-953",
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"abstract": "The National Ignition Facility (NIF), a laser-based Inertial Confinement Fusion (ICF) experiment designed to achieve thermonuclear fusion ignition and burn in the laboratory, will soon be completed at the Lawrence Livermore National Laboratory. Experiments designed to accomplish the NIF\u2019s goal will commence in 2010, using laser energies of 1 to 1.3 MJ. Fusion yields of the order of 10 to 35 MJ are expected soon thereafter. We propose that a laser system capable of generating fusion yields of 35 to 75 MJ at 10 to 15 Hz (i.e., \u2248 350- to 1000-MW fusion and \u2248 1.3 to 3.6 x 1020 n/s), coupled to a compact subcritical fission blanket, could be used to generate several GW of thermal power (GWth) while avoiding carbon dioxide emissions, mitigating nuclear proliferation concerns and minimizing the concerns associated with nuclear safety and long-term nuclear waste disposition. This Laser Inertial Fusion Energy (LIFE) based system is a logical extension of the NIF laser and the yields expected from the early ignition experiments on NIF. The LIFE concept is a once-through, self-contained closed fuel cycle and would have the following characteristics: (1) eliminate the need for uranium enrichment; (2) utilize over 90% of the energy content of the nuclear fuel; (3) eliminate the need for spent fuel chemical separation facilities; (4) maintain the fission blanket subcritical at all times (keff <0.90); and (5) minimize future requirements for deep underground geological waste repositories and minimize actinide content in the end-of-life nuclear waste below the (the lowest). Options to burn natural or depleted U, Th, U/Th mixtures, Spent Nuclear Fuel (SNF) without chemical separations of weapons-attractive actinide streams, and excess weapons Pu or highly enriched U (HEU) are possible and under consideration. Because the fission blanket is always subcritical and decay heat removal is possible via passive mechanisms, the technology is inherently safe. Many technical challenges must be met, but a LIFE solution could provide a sustainable path for worldwide growth of nuclear power for electricity production and hydrogen generation.",
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"abstract": "Part II of this special edition contains the remaining 11 papers arising from a Hooke discussion meeting held in March 2020 devoted to exploring the current status of inertial confinement fusion research worldwide and its application to electrical power generation in the future, via the development of an international inertial fusion energy programme. It builds upon increased coordination within Europe over the past decade by researchers supported by the EUROFusion Enabling Research grants, as well as collaborations that have arisen naturally with some of America's and Asia's leading researchers, both in the universities and national laboratories. The articles are devoted to informing an update to the European roadmap for an inertial fusion energy demonstration reactor, building upon the commonalities between the magnetic and inertial fusion communities' approaches to fusion energy. A number of studies devoted to understanding the physics barriers to ignition on current facilities are then presented. The special issue concludes with four state-of-the-art articles describing recent significant advances in fast ignition inertial fusion research. This article is part of a discussion meeting issue 'Prospects for high gain inertial fusion energy (part 2)'.",
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"abstract": "Configuration optimization is carried out for the heliotron-type fusion energy reactor FFHR. One of the important issues is to find sufficient clearances between the ergodic region outside the nested magnetic surfaces and blankets at the inboard side of the torus so that direct losses of alpha particles are minimized and the heat flux on the first walls is reduced. The latest design has a fairly large major radius Rc \u223c 17 m of the helical coils in order to satisfy this condition. It has been found, as an alternative design, that equivalent clearances are obtained with Rc = 15 m by employing a lower helical pitch parameter and splitting the helical coils in the poloidal cross-section at the outboard side. Furthermore, splitting the helical coils provides another modified configuration at Rc \u223c 17 m that ensures magnetic well formation in the fairly large nested magnetic surfaces with outward shifted configurations. From the engineering viewpoint, we propose that such helical coils be constructed by prefabricating half-pitch segments using high-temperature superconductors; the segments are then to be assembled on site with joints.",
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"abstract": "Abandoning superconductors for magnetic fusion reactors and instead using resistive magnet designs based on cheap copper or aluminum conductor material operating at \u201croom temperature\u201d (300\u00b0K) can reduce the capital cost per unit fusion power and simplify plant operations.1 By increasing unit size well beyond that of present MFE. conceptual designs using superconducting electromagnets, the recirculating power fraction needed to operate resistive electromagnets can be made as close to zero as needed for economy without requiring superconductors. Other advantages of large fusion plant size, such as very long inductively driven pulses, may also help reduce the cost per unit fusion power.2",
"URL": "https://digital.library.unt.edu/ark:/67531/metadc672278/m2/1/high_res_d/2684.pdf",
"title": "Improved Magnetic Fusion Energy Economics via Massive Resistive Electromagnets",
"year_published": 1998,
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"Resistive touchscreen",
"Fusion power",
"Nuclear engineering",
"Magnet",
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"abstract": "Some aspects of e-beam-pumped KrF laser physics and technology are considered with an impact on Fusion Test Facility design. These includes fluorescence and transient absorption measurements in KrF gain medium aimed at elaborating the kinetic model of large-scale amplifiers, studying the radiation stability of laser and target chamber optics, development of fluorine-resistant high-optical-strength protective coatings for laser windows.",
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"title": "Quests for inertial fusion energy conducted at GARPUN KrF laser facility",
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"abstract": "This paper outlines a strategy to significantly enhance scientific collaborations in both Fusion Energy Sciences and in High-Energy Physics through the development and deployment of new tools and technologies into working environments. This strategy is divided into two main elements, collaborative workspaces and secure computational services. Experimental and theory/computational programs will greatly benefit through the provision of a flexible, standards-based collaboration space, which includes advanced tools for ad hoc and structured communications, shared applications and displays, enhanced interactivity for remote data access applications, high performance computational services and an improved security environment. The technologies developed should be prototyped and tested on the current generation of experiments and numerical simulation projects. At the same time, such work should maintain a strong focus on the needs of the next generation of mega-projects, ITER and the ILC. Such an effort needs to leverage existing computer science technology and take full advantage of commercial software wherever possible. This paper compares the requirements of FES and HEP, discuss today's solutions, examine areas where more functionality is required, and discuss those areas with sufficient overlap in requirements that joint research into collaborative technologies will increase the benefit to both.",
"URL": "https://inis.iaea.org/search/search.aspx?orig_q=RN:38033869",
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"abstract": "The National Ignition Facility (NIF), a laser-based Inertial Confinement Fusion (ICF) experiment designed to achieve thermonuclear fusion ignition and burn in the laboratory, will soon be completed...",
"URL": "http://web.mit.edu/fusion-fission/HybridsPubli/LIFE_TOFE/Moses.pdf",
"title": "A Sustainable Nuclear Fuel Cycle Based on Laser Inertial Fusion Energy",
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"abstract": "A system which can mass produce millimetre sized spherical polymer shells economically and with high precision will be a great step towards the Inertial Fusion Energy goal. Microfluidics has shown itself to be a disruptive technology, where a rapid and continuous production of compound emulsions can be processed into such shells. Planar emulsion generators co-flow-focus in one step (COFON) and cascaded co-flow- focus (COFUS) enable millimetre compound emulsions to be produced using a one or two step formation process respectively. The co-flow-focus geometry uses symmetric and curved carrier fluid entrance walls to create a focusing orifice-minima and a carrier flow which aids movement and shaping of the dispersed fluid(s) towards the outlet, whilst maintaining operation in the dripping regime. Precision concentric alignment of these compound emulsions remains one of the greatest challenges. However steps to solve this passively using curved channel modulation to perturbate the emulsion have shown that rapid alignment can be achieved. Issues with satellite droplet formation, repeatability of the emulsion generation and cost are also addressed.",
"URL": "http://ui.adsabs.harvard.edu/abs/2016JPhCS.713a2011I/abstract",
"title": "A novel microfluidic system for the mass production of Inertial Fusion Energy shells",
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"abstract": "Krypton fluoride (KrF) lasers produce highly uniform beams at 248?nm, allow the capability of 'zooming' the spot size to follow an imploding pellet, naturally assume a modular architecture and have been developed into a pulsed-power-based industrial technology that readily scales to a fusion power plant sized system. There are two main challenges for the fusion power plant application: to develop a system with an overall efficiency of greater than 6% (based on target gains of 100) and to achieve a durability of greater than 3 ? 108 shots (two years at 5?Hz). These two issues are being addressed with the Electra (700?J, 5?Hz) and Nike (3000?J, single shot) KrF lasers at the Naval Research Laboratory. Based on recent advances in pulsed power, electron beam generation and transport, hibachi (foil support structure) design and KrF physics, wall plug efficiencies of greater than 7% should be achievable. Moreover, recent experiments show that it may be possible to realize long lived electron beam diodes using ceramic honeycomb cathodes and anode foils that are convectively cooled by periodically deflecting the laser gas. This paper is a summary of the progress in the development of the critical KrF technologies for laser fusion energy.",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/44/12/S16",
"title": "Repetitively pulsed, high energy KrF lasers for inertial fusion energy",
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"abstract": "Abandoning superconductors for magnetic fusion reactors and instead using resistive magnet designs based on cheap copper or aluminum conductor material operating at \"room temperature\" (300 K) can reduce the capital cost per unit fusion power and simplify plant operations. By increasing unit size well beyond that of present magnetic fusion energy conceptual designs using superconducting electromagnets, the recirculating power fraction needed to operate resistive electromagnets can be made as close to zero as needed for economy without requiring superconductors. Other advantages of larger fusion plant size, such as very long inductively driven pulses, may also help reduce the cost per unit fusion power.",
"URL": "https://digital.library.unt.edu/ark:/67531/metadc672278/m2/1/high_res_d/2684.pdf",
"title": "Improved Magnetic Fusion Energy Economics via Massive Resistive Electromagnets",
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"abstract": "The sheared-flow-stabilized (SFS) Z-pinch concept is on a path to commercialization at Zap Energy. Recent experiments on the Fusion Z-pinch Experiment (FuZE) and newly commissioned FuZE-Q devices are advancing the state of the art in pinch current, stable plasma duration, and deuterium\u2013deuterium fusion neutron production. The SFS Z-pinch configuration offers the promise of a compact fusion device owing to its simple geometry, unity beta, and absence of external magnetic field coils. In addition to a robust experimental program pushing plasma performance toward breakeven conditions, Zap Energy has parallel programs developing power handling systems suitable for future power plants. Technologies under development include high-repetition-rate pulsed power, high-duty-cycle electrodes, and liquid metal wall systems. The issue of electrode durability in future SFS Z-pinch power plants is elaborated on and compared with plasma material interaction regimes in other industrial processes and fusion energy systems.",
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"title": "Electrode durability and sheared-flow-stabilized Z-pinch fusion energy",
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"sentence": "The issue of electrode durability in future SFS Z-pinch power plants is elaborated on and compared with plasma material interaction regimes in other industrial processes and fusion energy systems.",
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"abstract": "A power plant based on a spheromak device using liquid walls is analyzed. We assume a spheromak configuration can be made and sustained by a steady plasma gun current, which injects particles, curr...",
"URL": "http://www.osti.gov/scitech/biblio/20849533-spheromak-magnetic-fusion-energy-power-plant-thick-liquid-walls",
"title": "Spheromak Magnetic Fusion Energy Power Plant with Thick Liquid-Walls",
"year_published": 2003,
"fields_of_study": [
"Magnetic field",
"Electric current",
"Magnetic confinement fusion",
"Nuclear physics",
"Materials science",
"Power density",
"Fusion power",
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"first_author": "Ralph W. Moir",
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"abstract": "The so-called 'threat spectra' of an inertial fusion energy (IFE) high gain target (neutron, x-ray, and ion energy fraction and particle spectra) are the usual starting point for IFE reactor conceptual design. The threat spectra are typically computed using the same radiation hydrodynamics and thermonuclear burn computer simulation codes used to compute implosion, ignition and burn. We analyze the validity of this model for simulating the expansion of the direct drive IFE target plasma and for computing threat spectra. Particular attention is paid to the collisionality of the expanding plasma.",
"URL": "https://www.tandfonline.com/doi/full/10.13182/FST05-A836",
"title": "High Energy Density Simulations for Inertial Fusion Energy Reactor Design",
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"abstract": "We report on a new class of laser amplifiers for inertial confinement fusion (ICF) drivers based on a Yb:YAG ceramic disk in an edge-pumped configuration and cooled by a high-velocity gas flow. The Yb lasant offers very high efficiency and low waste heat. The ceramic host material has a thermal conductivity nearly 15-times higher than the traditionally used glass and it is producible in sizes suitable for a typical 10- to 20-kJ driver beam line. The combination of high lasant efficiency, low waste heat, edge-pumping, and excellent thermal conductivity of the host, enable operation at 10 to 20 Hz at over 20% wall plug efficiency while being comparably smaller and less costly than recently considered face-pumped alternative drivers using Nd:glass, Yb:S-FAP, and cryogenic Yb:YAG. Scalability of the laser driver over a broad range of sizes is presented.",
"URL": "https://proceedings.spiedigitallibrary.org/proceeding.aspx?articleid=2505504",
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"Materials science",
"Fusion power",
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"abstract": "Induction core alloys are evaluated that are appropriate for heavy-ion induction accelerators to drive heavy-ion inertial fusion (HIF) power plants. Parameters evaluated include the usable flux swing and the energy loss over a range of magnetization rates of $\\ensuremath{\\sim}{10}^{5}--{10}^{7}\\mathrm{T}/\\mathrm{s}$, corresponding to pulse durations of $\\ensuremath{\\sim}20$ to $0.2\\ensuremath{\\mu}\\mathrm{s}$, respectively. The usable flux swing, for minimum core losses, extends from near the reversed remanent field to about 80% of the saturation field. The usable flux swing is enhanced, with little increase in losses, by annealing the core after winding. Maintaining low energy loss at high magnetization rates requires insulation to block interlaminar eddy currents. To obtain annealed cores with a high ratio of remanent to saturation magnetic field, the insulation must withstand annealing temperatures and apply minimum mechanical stress to the core during cooldown. We find that commercially available insulating coatings for amorphous metals either break down near ${10}^{6}\\mathrm{T}/\\mathrm{s}$ (a factor of 10 below the requirement), or do not achieve the maximum remanent field and hence the usable flux swing after annealing. More satisfactory coatings are available for silicon steel and nanocrystalline alloys, which could have applications in HIF. Amorphous alloys are capable of meeting most HIF needs, especially with improved coatings.",
"URL": "http://ui.adsabs.harvard.edu/abs/2002PhRvS...5h0401M/abstract",
"title": "Induction core alloys for heavy-ion inertial fusion-energy accelerators",
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"Amorphous metal",
"Eddy current",
"Nanocrystalline material",
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"Saturation (magnetic)",
"Fusion power",
"Condensed matter physics",
"Magnetization",
"Nuclear magnetic resonance",
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{
"abstract": "Abstract The most serious challenges in the design of chambers for inertial fusion energy (IFE) are: (1) protecting the first wall from fusion energy pulses on the order of several hundred megajoules released in the form of X-rays, target debris, and high energy neutrons; and (2) operating the chamber at a pulse repetition rate of 5\u201310\u00a0Hz (i.e. re-establishing the wall protection and chamber conditions needed for beam propagation to the target between pulses). In meeting these challenges, designers have capitalized on the ability to separate the fusion burn physics from the geometry and environment of the fusion chamber. Most recent conceptual designs use gases or flowing liquids inside the chamber. Thin liquid layers of molten salt or metal and low pressure, high-Z gases can protect the first wall from X-rays and target debris, while thick liquid layers have the added benefit of protecting structures from fusion neutrons thereby significantly reducing the radiation damage and activation. The use of thick liquid walls is predicted to: (1) reduce the cost of electricity by avoiding the cost and down time of changing damaged structures; and (2) reduce the cost of development by avoiding the cost of developing a new, low-activation material. Various schemes have been proposed to assure chamber clearing and renewal of the protective features at the required pulse rate. Representative chamber concepts are described, and key technical feasibility issues are identified for each class of chamber. Experimental activities (past, current and proposed) to address these issues and technology research and development needs are discussed.",
"URL": "https://www.sciencedirect.com/science/article/pii/S0920379697001324",
"title": "Chamber technology concepts for inertial fusion energy\u2014three recent examples",
"year_published": 1998,
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"Nuclear engineering",
"Current (fluid)",
"Fusion",
"Beam (structure)",
"Inertial frame of reference",
"Fusion power",
"Molten salt",
"Pulse (physics)",
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"first_author": "Wayne R. Meier",
"scholarly_citations_count": 2,
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"abstract": "A coordinated, focused effort is underway to develop Laser Inertial Fusion Energy. The key components are developed in concert with one another and the science and engineering issues are addressed concurrently. Recent advances include: target designs have been evaluated that show it could be possible to achieve the high gains (>100) needed for a practical fusion system.These designs feature a low-density CH foam that is wicked with solid DT and over-coated with a thin high-Z layer. These results have been verified with three independent one-dimensional codes, and are now being evaluated with two- and three-dimensional codes. Two types of lasers are under development: Krypton Fluoride (KrF) gas lasers and Diode Pumped Solid State Lasers (DPSSL). Both have recently achieved repetitive 'first light', and both have made progress in meeting the fusion energy requirements for durability, efficiency, and cost. This paper also presents the advances in development of chamber operating windows (target survival plus no wall erosion), final optics (aluminium at grazing incidence has high reflectivity and exceeds the required laser damage threshold), target fabrication (demonstration of smooth DT ice layers grown over foams, batch production of foam shells, and appropriate high-Z overcoats), and target injection (new facility for target injection and tracking studies).",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/43/12/015/pdf",
"title": "Fusion energy with lasers, direct drive targets, and dry wall chambers",
"year_published": 2003,
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"Materials science",
"Fusion power",
"Batch production",
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"abstract": "Limitations in operating conditions, primarily the steady-state operating temperature, of silicon carbide-based ceramics and composites for applications to structural and functional components in fusion blanket systems were critically examined based on the latest experimental results. Irradiation-induced high temperature swelling and irradiation creep were identified to be the likely factors limiting the upper temperature bound for structural applications, whereas irradiation-induced thermal conductivity degradation was identified to be the primary factor to limit the lower temperature bound when substantial heat flux is anticipated. For the application to flow channel inserts in liquid metal blankets, insulating properties will likely limit the upper temperature bound, whereas the lower temperature bound may be limited by swelling-induced secondary stress. Additionally, key scientific issues which need to be addressed for the better definition of design limitations were identified.",
"URL": "https://www.ans.org/pubs/journals/fst/a_9049",
"title": "Operating Temperature Window for SiC Ceramics and Composites for Fusion Energy Applications",
"year_published": 2009,
"fields_of_study": [
"Operating temperature",
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"Creep",
"Heat flux",
"Composite material",
"Materials science",
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"Blanket",
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"first_author": "Yutai Katoh",
"scholarly_citations_count": 12,
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"abstract": "IAEA-OV/3-4 U.S. Heavy Ion Beam Science towards Inertial Fusion Energy B.G. Logan 1), D. Baca 1), J.J. Barnard 2), F.M. Bieniosek 1), C. Burkhart 6), C.M. Celata 1), E. Chacon-Golcher 1), R.H. Cohen 2), R.C. Davidson 3), P. Efthimion 3), A. Faltens 1), A. Friedman 2), L. Grisham 3), D.P Grote 2), I. Haber 4), E. Henestroza 1), I. Kaganovich 3), R.A. Kishek 4), J.W. Kwan 1), E.P. Lee 1), W.W. Lee 3), M. Leitner 1), S.M. Lund 2), W.R. Meier 2), A.W. Molvik 2), P.G. O\u2019Shea 4), C. Olson 8), R.E. Olson 7), L.R. Prost 1), H. Qin 3), M. Reiser 4), D. Rose 5), G. Sabbi 1), P.A Seidl 1), W.M. Sharp 2), D.B. Shuman 1), J-L. Vay 1), W.L. Waldron 1), D. Welch 5), G.A. Westenskow 2), S.S. Yu 1) 1) Lawrence Berkeley National Laboratory, Berkeley, CA 2) Lawrence Livermore National Laboratory, Livermore, CA 3) Princeton Plasma Physics Laboratory, Princeton, NJ 4) University of Maryland, College Park, MD 5) Mission Research Corporation, Albuquerque, NM 6) First Point Scientific, Inc., Agoura Hills, CA 7) University of Missouri, Rolla, MO 8) Sandia National Laboratory, Albuquerque, NM Email contact of main author: bglogan@lbl.gov Abstract. Significant experimental and theoretical progress in the U.S heavy-ion fusion (HIF) program is reported in modeling and measurements of intense space-charge-dominated heavy ion and electron beams. Measurements of the transport of a well-matched and aligned high current (0.2A) 1.0 MeV potassium ion beam through 10 electric quadrupoles, with a fill factor of 60%, shows no emittance growth within experimental measurement uncertainty, as expected from the simulations. Another experiment shows that passing a beam through an aperture can reduce emittance to near the theoretical limits, and that plasma neutralization of the beam\u2019s space-charge can greatly reduce the focal spot radius. Measurements of intense beamlet current density, emittance, charge-state purity, and energy spread from a new, high-brightness, Argon plasma source for HIF experiments are described. New theory and simulations of neutralization of intense beam space charge with plasma in various focusing chamber configurations indicate that near-emittance-limited beam focal spot sizes can be obtained even with beam perveance an order of magnitude higher than in earlier HIF focusing experiments. 1. Introduction This article reports results from the last two years of experiments and simulations with space- charge-dominated heavy ion and electron beams relevant to understanding the behavior of the high-brightness heavy ion beams ultimately required to drive high-gain inertial fusion targets. The success of inertial fusion energy (IFE) with heavy ions will require high-brightness and peak power accelerators [1], high-gain target designs [2], methods to produce, and inject such targets at 5 Hz pulse rates and targets that can be mass produced at low cost [3], and long- lasting, low-activation chambers that can protect the walls and focusing magnets from repeated fusion energy bursts [3]. Heavy ion beam research is carried out under the auspices of the Heavy-Ion Fusion Virtual National Laboratory (HIF-VNL) by Lawrence Berkeley National Laboratory, Lawrence Livermore National Laboratory, and Princeton Plasma Physics Laboratory, and other HIF beam science research is performed by the University of",
"URL": "https://www.osti.gov/servlets/purl/815501/",
"title": "U.S. Heavy Ion Beam Science towards inertial fusion energy",
"year_published": 2002,
"fields_of_study": [
"Ion",
"Electron",
"Beam (structure)",
"Nuclear physics",
"Chemistry",
"Aperture",
"Fusion power",
"Perveance",
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"abstract": "Driver beams must hit targets accurately in an inertial fusion energy power plant. Current requirements are less than \u00b1200 \u03bcm for indirect drive targets and \u00b120 \u03bcm for direct drive targets. A recent target tracking and position prediction experiment was carried out using indirect drive target sized projectiles.' The results of that scaled experiment extrapolate to a standard deviation of 220 \u03bcm error in position prediction at power plant size. Greater accuracy will be required, especially for direct drive targets. Greater standoff between the detectors and the targets (previously about 3 cm) will also be required to allow for detector shielding. Diffraction effects are expected to be more important with greater standoff and accuracy requirements. An improved optical target tracking and position prediction system is being designed, as part of the Target Injection and Tracking Experiment at General Atomics, to achieve the above requirements. Concepts for improving accuracy include the use of multiple photodiode arrays, a temperature controlled environment, vibration-limiting detector mounts, additional detector stations, improved electronic noise suppression, and constant-brightness laser light sources. The current status of this design work is presented.",
"URL": "https://www.tandfonline.com/doi/pdf/10.13182/FST01-A11963317",
"title": "Design of an inertial fusion energy target tracking and position prediction system",
"year_published": 2001,
"fields_of_study": [
"Position (vector)",
"Nuclear physics",
"Electromagnetic shielding",
"Standard deviation",
"Fusion power",
"Acoustics",
"Computer science",
"Tracking (particle physics)",
"Power station",
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"first_author": "Ronald W. Petzoldt",
"scholarly_citations_count": 11,
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"abstract": "Inorganic membrane based techniques have been applied to various gas separation processes in the chemical process industries, especially in the separation of hydrogen fromhydrocarbons and carbon dioxide in synthesis gas. In the field of fusion energy research, the separation of hydrogen isotopes, especially deuterium and tritium from a helium stream is of great importance since helium is the inert carrier gas that will purge the tritium bred during fusion from the lithium-containing solid and liquid breeder materials. The efficiency of separation of tritium from helium is a major factor that governs the success of fusion energy systems. Membrane based processes have been studied quite extensively for this separation because of the very high selectivity for hydrogen isotopes that is obtained in this technique as compared to more conventional methods. This review summarises current information about the types of membranes studied for hydrogen separation, their synthesis and characterization methods, the desirable properties of these membranes and the technological difficulties associated with this separation method. Specifically, the suitability of different types ofmembranes for tritiumremoval fromheliumis ascertained in this work.",
"URL": "https://www.tsijournals.com/abstract/inorganic-membranes-for-hydrogen-isotopehelium-separation-in-fusion-energy-research-1667.html",
"title": "Inorganic membranes for hydrogen isotope-helium separation in fusion energy research",
"year_published": 2014,
"fields_of_study": [
"Analytical chemistry",
"Gas separation",
"Chemistry",
"Syngas",
"Fusion power",
"Membrane",
"Chemical engineering",
"Hydrogen",
"Helium",
"Deuterium",
"Tritium"
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"first_author": "Rupsha Bhattacharyya",
"scholarly_citations_count": 1,
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"abstract": "DIII-D has made significant advances in the scientific basis for fusion energy. The physics mechanism of resonant magnetic perturbation (RMP) edge localized mode (ELM) suppression is revealed as field penetration at the pedestal top, and reduced coil set operation was demonstrated. Disruption runaway electrons were effectively quenched by shattered pellets; runaway dissipation is explained by pitch angle scattering. Modest thermal quench radiation asymmetries are well described NIMROD modelling. With good pedestal regulation and error field correction, low torque ITER baselines have been demonstrated and shown to be compatible with an ITER test blanket module simulator. However performance and long wavelength turbulence degrade as low rotation and electron heating are approached. The alternative QH mode scenario is shown to be compatible with high Greenwald density fraction, with an edge harmonic oscillation demonstrating good impurity flushing. Discharge optimization guided by the EPED model has discovered a new super H-mode with doubled pedestal height. Lithium injection also led to wider, higher pedestals. On the path to steady state, 1 MA has been sustained fully noninductively with \u03b2N = 4 and RMP ELM suppression, while a peaked current profile scenario provides attractive options for ITER and a \u03b2N = 5 future reactor. Energetic particle transport is found to exhibit a critical gradient behaviour. Scenarios are shown to be compatible with radiative and snowflake divertor techniques. Physics studies reveal that the transition to H mode is locked in by a rise in ion diamagnetic flows. Intrinsic rotation in the plasma edge is demonstrated to arise from kinetic losses. New 3D magnetic sensors validate linear ideal MHD, but identify issues in nonlinear simulations. Detachment, characterized in 2D with sub-eV resolution, reveals a radiation shortfall in simulations. Future facility development targets burning plasma physics with torque free electron heating, the path to steady state with increased off axis currents, and a new divertor solution for fusion reactors.",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/55/10/104017/pdf",
"title": "DIII-D research to address key challenges for ITER and fusion energy",
"year_published": 2015,
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"abstract": "Abstract\n The cost and complexity of large, high-field superconducting magnet modules and related subsystems comprise 30% to 60% of the fusion reactor core capital cost. The strategic plan for the U.S. burning plasma research, the Fusion Energy Sciences Committee Report (FESAC) \u201cPower the Future: Fusion and Plasmas\u2019', and 2021 NASEM report \u201cKey Goals and Innovations needed for a U.S. Fusion Pilot Plant\u201d recommends that the U.S. pursue innovative science and technology to enable construction of a Fusion Pilot Plant (FPP) that produces net electricity from fusion at reduced capital cost. To achieve this, a novel combination of lower-cost high temperature superconductors (HTS) in cable configurations with co-wound reinforcement for higher current density are being investigated using a simplified construction strategy to produce compact stable coils. They would be capable of generating 20 T at up to 10-20 K. Small-scale, inexpensive test coils and prototypes will help develop each feature and validate cabled conductor design models. The near term goal is to validate engineering approaches, scientific models and fabrication capabilities applicable to fusion reactor development such as U.S. fusion nuclear science facility (FNSF), sustained high-power density tokamak facility (SHPD) and FPP designs. The design options include lower-cost, high-strength, quench resistant REBCO or Bi-2212 cables in an all metal coil design that simplifies HTS coil construction and quench protection system, with co-wound reinforcements that integrate stress management in HTS cable design and provides thermal mass to help prevent quench damage.",
"URL": "NaN",
"title": "Low cost, simpler HTS cable conductors for fusion energy systems",
"year_published": 2022,
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"Nuclear engineering",
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"abstract": "The fusion energy spectrum was discussed;the fault diagnosis method for rotary machinery based on fusion energy spectrum was put forward.Engineering practice indicated that the fault diagnosis accuracy based on fusion energy spectrum was higher than that based on the information of single channel.",
"URL": "http://en.cnki.com.cn/Article_en/CJFDTOTAL-WXYJ201003046.htm",
"title": "Study on Fault Diagnosis for Rotary Machinery Based on Fusion Energy Spectrum",
"year_published": 2010,
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"abstract": "The use of aneutronic fusion fuels, such as D-3He, is shown to require much higher values of plasma beta and much longer confinement times, in a system of smaller size, than for the conventional D-T fuel. It has been suggested that direct conversion might help to offset these disadvantages. We discuss generic features of the conversion process. We conclude that direct conversion at high efficiency, required for aneutronic fuels, appears to be feasible only in open field line configurations, which do not have adequate plasma confinement qualities.",
"URL": "https://iopscience.iop.org/article/10.1088/0741-3335/36/8/003",
"title": "Generic issues for direct conversion of fusion energy from alternative fuels",
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"abstract": "We have reported the present status in the development of a position measurement unit (PMU) for a flying inertial fusion energy (IFE) target. The PMU, which uses Arago spot phenomena, is designed to have a measurement accuracy smaller than 1 \u03bcm. By employing divergent, pulsed orthogonal laser beam illumination, we can measure the time and the target position at the pulsed illumination. The two-dimensional Arago spot image is compressed into one-dimensional image by a cylindrical lens for real-time processing. The PMU are set along the injection path of the flying target. The local positions of the target in each PMU are transferred to the controller and analysed to calculate the target trajectory. Two methods are presented to calculate the arrival time and the arrival position of the target at the reactor centre.",
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"title": "Development of position measurement unit for flying inertial fusion energy target",
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"abstract": "In a global effort, the key players have combined their RD the proposed qualification techniques for fusion in-vessel and heat removal systems are reviewed.",
"URL": "https://pennstate.pure.elsevier.com/en/publications/material-processing-and-testing-of-plasma-interactive-components-",
"title": "Material processing and testing of plasma-interactive components for fusion energy systems",
"year_published": 2005,
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"Materials science",
"Key (cryptography)",
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"abstract": "The status of laser-driven inertial confinement fusion research is briefly reviewed. The recent major achievement of fusion energy release exceeding the energy delivered by the laser to the fuel (Hurricane O. et al., Nature, 506 (2014) 343), and the efforts towards ignition demonstration using indirect-drive are discussed. Physics model reliability is addressed. The potentials of alternative schemes, in particular direct-drive shock ignition, are also illustrated.",
"URL": "https://epljournal.edpsciences.org/articles/epl/abs/2015/04/epl16938/epl16938.html",
"title": "Light for controlled fusion energy: A perspective on laser-driven inertial fusion",
"year_published": 2015,
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{
"sentence": "The potentials of alternative schemes, in particular direct-drive shock ignition, are also illustrated.",
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{
"abstract": "Physics and technology of Krypton Fluoride (KrF) laser have been studied experimentally and theoretically to improve its efficiency and to increase a lifetime, and thus to verify the challenge of KrF laser for Inertial Fusion Energy (IFE). Experiments were performed with e-beam-pumped multistage 100-J output energy GARPUN KrF laser facility and 200-A/cm 2 current density EL-1 electron gun, both operating at P.N. Lebedev Physical Institute. They formed the database for verification of numerical codes capable to predict IFE-scale KrF drivers. Monte Carlo code was developed to calculate e-beam energy deposition inside GARPUN laser chamber while a quasistationary numerical KrF laser code based on generalized \"forward-back\" multi-direction approximation for radiation transfer equation was used to describe amplification of nanosecond pulses and amplified spontaneous emission (ASE). Long-lived absorption in UV optical materials induced by fast electrons and bremsstrahlung X-ray radiation was measured at EL-1 electron gun with total fluence of ionizing radiation up to 20.6 kJ/cm 2 . Using these data together with measurements and scaling of bremsstrahlung X-ray yield, we can predict that the most stable windows of IFE-scale KrF laser driver would be able to withstand no less than 2 \u00d7 10 6 shots. Fluorine-resistant coatings onto fused silica windows of KrF laser were developed and demonstrated damage thresholds as high as 29 J/cm 2 in test experiments with large 13 x 13-mm uniformly irradiated spot.",
"URL": "https://ui.adsabs.harvard.edu/abs/2006JPhy4.133..567Z/abstract",
"title": "Physical and technological issues of KrF laser drivers for inertial fusion energy",
"year_published": 2006,
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"Radiation",
"Electron gun",
"Chemistry",
"Amplified spontaneous emission",
"Fusion power",
"Nanosecond",
"Laser",
"Absorption (electromagnetic radiation)",
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"first_author": "Vladimir D. Zvorykin",
"scholarly_citations_count": 5,
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{
"abstract": "Adiabatic plasma heating by the implosion of a compressible, cylindrical, end-plugged liner is studied by means of an approximate analytical model and by a computer code that employs sophisticated equation-of-state tables for the metal liner. The model contains cylindrical convergence effects and an approximate but realistic equation-of-state. Analytic expressions are derived for the pressure profile in the liner, for the internal energy of the liner, for the maximized fusion energy output of the enclosed D-T plasma, for the corresponding optimized initial conditions, and for the resulting peak pressure, final radius and thickness, and burn time. In this idealized model that ignores losses, energy transfer efficiencies (liner to plasma) of 70% are found, and a gain of 4 (ratio of fusion energy to liner energy) can occur with an initial liner energy of 300 MJ m\u22121. Finally, losses from the plasma are briefly discussed.",
"URL": "https://ui.adsabs.harvard.edu/abs/1979NucFu..19..155G/abstract",
"title": "Adiabatic plasma heating and fusion-energy production by a compressible fast liner",
"year_published": 1979,
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"Adiabatic process",
"Atomic physics",
"Energy (signal processing)",
"Materials science",
"Implosion",
"Fusion power",
"Mechanics",
"Internal energy",
"Plasma",
"Radius",
"Compressibility"
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"first_author": "R.A. Gerwin",
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"abstract": "The first 17 articles published in this issue of Nuclear Fusion form a special section with the aim of monitoring the progress made in experiments on fusion physics that have been conducted worldwide up to the end of 2002. These articles are based on overview reports from the various experimental teams presented at the Fusion Energy Conference (FEC-2002). This conference was organized by the IAEA together with the French host organization CEA and was held in Lyon, France, in October 2002. During 2003 the conference overviews have been rewritten and extended for the purpose of this special section and submitted to our standard double-referee peer review. While not all teams have made use of this opportunity, a sufficiently large number have, so that this issue presents a reasonably complete picture of the progress made since the FEC-2000 was held in Sorrento. The articles are arranged in the following sequence: Tokamaks: Performance: JT-60U, JET, DIII-D, ASDEX-U; Steady state/long pulse operation: Tore Supra, TRIAM; Heating methods: C-Mod (ICRH), TCV and T-10 (ECRH) and FTU (LHH + ECRH). Alternative magnetic confinement concepts: Stellarators: LHD; Reversed field pinches: MST. Inertial confinement: Direct drive. Two of the five summaries presented at the Lyon conference, which aim to report on the progress made in fusion physics, complete this special section. These summaries are structured along the lines of specific physics issues instead of specific devices: `Theory of magnetic confinement' and `Experiments in confinement and wave--plasma interaction'. I hope that this special section will give the interested reader an up-to-date picture of the progress made in nuclear fusion research.",
"URL": "http://iopscience.iop.org/0029-5515/43/12/E01/pdf/0029-5515_43_12_E01.pdf",
"title": "Special section containing overview reports from the 2002 Fusion Energy Conference",
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"Tokamak",
"Magnetic confinement fusion",
"Nanotechnology",
"Systems engineering",
"Fusion power",
"Tore Supra",
"Special section",
"Long pulse",
"Nuclear fusion"
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"abstract": "New approaches in target design have increased the possibility that useful fusion power can be generated with sub-MJ lasers. We have performed many ID and 2D simulations that examine the characteristics of target designs for sub-MJ lasers. These designs use the recently-proposed shock-ignition target scheme, which utilizes a separate high-intensity pulse to induce ignition. A promising feature of these designs is their significantly higher gains at lower energies (one dimensional (1D) gain~ 100 at E laser 250kJ) than can be expected for the conventional central ignition scheme. The results of these simulations are shown and we discuss the implications for target fabrication and laser design. Of particular interest are the constraints on the target and laser from asymmetries due to target imperfections and laser imprint. F.",
"URL": "https://www.ans.org/pubs/journals/fst/a_8930",
"title": "Direct Drive Fusion Energy Shock Ignition Designs for Sub-MJ Lasers",
"year_published": 2009,
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"Physics",
"Fabrication",
"Ignition system",
"Energy (signal processing)",
"Fusion power",
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"Nuclear fusion",
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"abstract": "The National Energy Research Scientific Computing Center (NERSC) was originally launched as a computing center for the exclusive support of magnetic confinement fusion research in the US. There is, thus, a long history of computational advances and successes that ties fusion scientists with NERSC and its staff. One example of the numerous computational achievements enabled by NERSC in this field is the development of the global gyrokinetic particle-in-cell approach for the simulation of turbulent transport in tokamak fusion devices. This article describes the historical evolution of this method and the codes implementing it, and the impact that NERSC had in their development and the scientific discoveries that they allow.",
"URL": "https://dblp.uni-trier.de/db/journals/cse/cse17.html#EthierCKLWLT15",
"title": "NERSC's Impact on Advances of Global Gyrokinetic PIC Codes for Fusion Energy Research",
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"abstract": "Aimed at the problem of reliable power supply and power transmission of spacecraft applications, the microwave and laser fusion energy transfer mechanism based on QoS and QoE guarantee was first proposed in this paper. NS2 software was used to simulate the wireless energy transmission network and the QoS level was obtained through the second-level fuzzy evaluation. The QoE guarantee of the power threshold based on the second diffraction region was firstly introduced. At the same time, the Beer transmission and the Markov model were used to respectively transmit the laser in the adjacent space. The attenuation effects and turbulence effects were calculated and simulated. The results showed that in the adjacent space, when the transmission distance is greater than 30 meters and less than 100 meters, the efficiency of fusion system increases up to 10%, avoiding electromagnetic environmental pollution and energy loss caused by excessive energy transmission, and achieving efficient and green transmission of energy in the adjacent space.",
"URL": "https://dpi-proceedings.com/index.php/dtcse/article/viewFile/26291/25705",
"title": "Microwave and Laser Fusion Energy-Transfer Mechanism Based on QoS and QoE Guarantee",
"year_published": 2018,
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"Inertial confinement fusion",
"Electric power transmission",
"Energy (signal processing)",
"Electronic engineering",
"Environmental pollution",
"Spacecraft",
"Computer science",
"Microwave",
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"Power transmission"
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"first_author": "Tianyi Zheng",
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"sentence": "The results showed that in the adjacent space, when the transmission distance is greater than 30 meters and less than 100 meters, the efficiency of fusion system increases up to 10, avoiding electromagnetic environmental pollution and energy loss caused by excessive energy transmission, and achieving efficient and green transmission of energy in the adjacent space.",
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"abstract": "An historical synopsis is provided of the NASA-Lewis research program on fusion energy for space power and propulsion systems. It was initiated to explore the potential applications of fusion energy to space power and propulsion systems. Some fusion related accomplishments and program areas covered include: basic research on the Electric Field Bumpy Torus (EFBT) magnetoelectric fusion containment concept, including identification of its radial transport mechanism and confinement time scaling; operation of the Pilot Rig mirror machine, the first superconducting magnet facility to be used in plasma physics or fusion research; operation of the Superconducting Bumpy Torus magnet facility, first used to generate a toroidal magnetic field; steady state production of neutrons from DD reactions; studies of the direct conversion of plasma enthalpy to thrust by a direct fusion rocket via propellant addition and magnetic nozzles; power and propulsion system studies, including D(3)He power balance, neutron shielding, and refrigeration requirements; and development of large volume, high field superconducting and cryogenic magnet technology.",
"URL": "http://hdl.handle.net/2060/19910012835",
"title": "The NASA-Lewis Program on Fusion Energy for Space Power and Propulsion, 1958\u20131978",
"year_published": 1991,
"fields_of_study": [
"Propulsion",
"Inertial confinement fusion",
"Physics",
"Aerospace engineering",
"Spacecraft propulsion",
"Superconducting magnet",
"Fusion power",
"Fusion rocket",
"Electromagnetic propulsion",
"Propellant"
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"first_author": "Norman R. Schulze",
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{
"abstract": "The path to fusion in the United States requires partnership between public and private sector. While the private sector provides the vigor to take some of the major steps necessary, there is a depth of expertise and capability in the public sector that is vital to resolving feasible approaches. As an open national user facility, DIII-D provides a crucial testbed to develop the required new technologies and approaches in relevant conditions. It has unparalleled potential to meet this challenge, thanks to its extreme flexibility and world leading diagnostics. This provides a basis to rapidly develop solutions that project to future reactors with confidence. The program has thus been redeveloped to enable public and private sector engagement and testing of new concepts. A new technology program has been launched to resolve plasma interacting technologies. With modest heating upgrades, the facility can confront the crucial \u201cIntegrated Tokamak Exhaust and Performance\u201d gap, to resolve core, exhaust and technology solutions together. The device is also being redeveloped as a training facility, with dedicated student run time, a mentorship program, and open access to all opportunity roles, part of wider efforts to diversify and open pathways through inclusion, access, and equity. This exciting agenda is enabling scientists and technology researchers to pioneer the solutions needed for a Fusion Pilot Plant (FPP) and ITER this decade. As a national user facility, DIII D has singular potential to provide the tools, teams, and insight necessary, to do its part in moving the United States rapidly toward the commercialization of fusion energy.",
"URL": "https://pubs.aip.org/aip/pop/article-pdf/doi/10.1063/5.0176729/18266084/120603_1_5.0176729.pdf",
"title": "DIII-D's role as a national user facility in enabling the commercialization of fusion energy",
"year_published": 2023,
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"Private sector",
"General partnership",
"Flexibility (engineering)",
"DIII-D",
"Systems engineering",
"Tokamak",
"Engineering management",
"Business",
"Physics",
"Engineering",
"Marketing",
"Political science",
"Finance",
"Economics",
"Plasma",
"Management",
"Quantum mechanics",
"Law"
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"abstract": "A European consortium of 15 laboratories across nine nations have worked together under the EUROFusion Enabling Research grants for the past decade with three principle objectives. These are: (a) investigating obstacles to ignition on megaJoule-class laser facilities; (b) investigating novel alternative approaches to ignition, including basic studies for fast ignition (both electron and ion-driven), auxiliary heating, shock ignition etc.; and (c) developing technologies that will be required in the future for a fusion reactor. The Hooke discussion meeting in March 2020 provided an opportunity to reflect on the progress made in inertial confinement fusion research world-wide to date. This first edition of two special issues seeks to identify paths forward to achieve high fusion energy gain. This article is part of a discussion meeting issue 'Prospects for high gain inertial fusion energy (part 1)'.",
"URL": "https://eprints.whiterose.ac.uk/168652/",
"title": "Prospects for high gain inertial fusion energy: an introduction to the first special edition",
"year_published": 2020,
"fields_of_study": [
"Inertial confinement fusion",
"Aerospace engineering",
"Ignition system",
"Inertial frame of reference",
"Fusion power",
"Auxiliary heating",
"Computer science",
"Laser",
"High-gain antenna",
"Shock (mechanics)"
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"first_author": "Peter Norreys",
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{
"abstract": "Direct-drive fusion with lasers is an attractive avenue for fusion energy. Simulations indicate there is potential for robust targets that have sufficient gain for energy. The envisioned power-plant laser systems would be highly modular allowing for development and testing of full-scale components prior to building the plant. In the United States there is an integrated program to develop the technologies for laser fusion energy including: high-repetition drivers (Electra krypton-fluoride (KrF) laser at NRL and Mercury diode-pumped solid-state laser at LLNL), target injection and fabrication, final optics, reaction chamber design and materials. This program takes advantage of the existing investment in lasers and target design by the Department of Energy as part of the stockpile stewardship program. Here we will discuss NRL contributions to the laser-fusion program including research on the KrF technology and the needed advanced target designs. We will also discuss our vision for a relatively low-risk and lower-cost development path to a fusion power plant using lasers.",
"URL": "https://www.osapublishing.org/viewmedia.cfm?uri=FiO-2003-MB2&seq=0",
"title": "Development path to fusion energy using direct drive with the krypton-fluoride laser",
"year_published": 2003,
"fields_of_study": [
"Modular design",
"Inertial confinement fusion",
"Fabrication",
"Aerospace engineering",
"Fusion",
"Fusion power",
"Krypton fluoride laser",
"Stockpile",
"Computer science",
"Laser"
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"first_author": "Stephen P. Obenschain",
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"abstract": "Abstract The high-current experiment (HCX) at LBNL is a driver scale single beam injector that provides a 1\u00a0MeV K + ion beam current of 0.18\u00a0A for 5\u00a0\u03bcs. It transports high-current beams with large fill factor (ratio of the maximum beam envelope radius to the beam pipe radius) and low emittance growth that are required to keep the cost of the power plant competitive and to satisfy the target requirements of focusing ion beams to high-power density. Beam interaction with the background gas and walls desorbs electrons that can multiply and accumulate, creating an electron cloud. This ubiquitous effect grows at higher fill factors and degrades the quality of the beam. We review simulations and diagnostics tools used to measure electron production, accumulation and its properties.",
"URL": "https://escholarship.org/uc/item/7xs0t0k2",
"title": "Electron cloud measurements in heavy-ion driver for HEDP and inertial fusion energy",
"year_published": 2007,
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"Ion",
"Electron",
"Beam (structure)",
"Atomic physics",
"Chemistry",
"Fusion power",
"Computational physics",
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"abstract": "Theory for a gridded inertial electrostatic confinement (IEC) fusion system is presented, which shows a net energy gain is possible if the grid is magnetically shielded from ion impact. A simplified grid geometry is studied, consisting of two negatively biased coaxial current-carrying rings, oriented such that their opposing magnetic fields produce a spindle cusp. Our analysis indicates that better than break-even performance is possible even in a deuterium-deuterium system at bench-top scales. The proposed device has the unusual property that it can avoid both the cusp losses of traditional magnetic fusion systems and the grid losses of traditional IEC configurations.",
"URL": "http://scitation.aip.org/content/aip/journal/pop/22/10/10.1063/1.4933213",
"title": "Fusion energy in an inertial electrostatic confinement device using a magnetically shielded grid",
"year_published": 2015,
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"Inertial electrostatic confinement",
"Physics",
"Ion",
"Grid",
"Fusion power",
"Cusp (singularity)",
"Computational physics",
"Coaxial",
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"Magnetic confinement fusion",
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"first_author": "J. N. Hedditch",
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"abstract": "The tritium breeding and energy absorption in an inertial fusion energy (IFE) reactor chamber have been investigated with variable coolant zone thickness using different materials. Examples are given for HYLIFE-II (an IFE reactor design) and for magnetohydrodynamic (MHD) energy conversion chambers using Flibe (Li[sub 2]BeF[sub 4]) as coolant. Investigations related to MHD are extended to the use of LiH, lithium, and Li17-Pb83 eutectic as working fluid. Natural lithium is used in all cases, except in the case of LiPb, for which both natural and enriched options were calculated. To achieve a useful energy density for energy conversion purposes with a sufficient tritium breeding ratio (TBR = 1.1 to 1.2), coolant zone thicknesses must be 25 cm for LiH, 50 to 60 cm for Flibe, and 80 cm for lithium. The use of Li17-Pb83 with natural lithium and with lithium enriched to 90% [sup 6]Li requires coolant zone thicknesses of 120 and 60 cm, respectively, to obtain a tritium breeding of TBR = 1.1, which gives an extremely low energy deposition density. This low density and the large coolant mass make LiPb unattractive for MHD and HYLIFE-II applications. 15 refs., 10 figs., 5 tabs.",
"URL": "https://www.ans.org/pubs/journals/fst/a_30245",
"title": "Neutronic Investigation of Inertial Fusion Energy Blankets for HYLIFE-II and Magnetohydrodynamic Applications",
"year_published": 1994,
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"Energy transformation",
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"abstract": "SOMBRERO (solid moving breeder reactor) is a conceptual design of a 1000 MW e laser-driven inertial fusion energy (IFE) power plant. An important goal of the original study was the achievement of a safe and environmentally attractive reactor of relatively simple design. However, recent work has pointed out some key issues involving safety that were not completely addressed at that time, and which need to be reviewed in order to maximize the SOMBRERO design attractiveness. The present work uses a set of computer codes traditionally used for magnetic fusion safety studies (CHEMCON, MELCOR), which have been adopted and adapted for use in IFE safety analysis. Here we consider a loss of flow accident (LOFA) combined with a simultaneous loss of vacuum accident (LOVA) produced by a breach in the confinement building. Although confinement failure would be a very unlikely event, it must be postulated in order to produce significant off-site doses. The CHEMCON code is used to simulate the long-term thermal transient in the reactor structures resulting from oxidation and radioactive decay heat. MELCOR is used to simulate a wide range of physical phenomena including thermal-hydraulics, heat transfer, aerosol physics and fusion product release and transport. As specified in the DOE Fusion Safety Standards, an off-site dose below 1 rem (10 mSv) is the requirement to avoid public sheltering and evacuation. The SOMBRERO accident analysis results will be evaluated according to this limit and suggestions will be made for improvements and future work.",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST01-A11963361",
"title": "Accident Doses Analysis of the Sombrero Inertial Fusion Energy Power Plant Design",
"year_published": 2001,
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"abstract": "Energy release by nuclear fusion reactions was first proposed in the context of theories explaining the energy source of stellar objects. Subsequently, laboratory experiments in the 1930's demonstrated the validity of such reactions. From the 1940's onward, efforts began to pursue the controlled & uncontrolled release of nuclear fusion energy for both civilian & military applications. While the military aspect of this technology was proved in the early 1950's, the civilian part, which focused on inventing different techniques to fuse light elements nuclei to produce power, found little success. The main reason for this was undertaking expensive & complicated fusion experiments without fully resolving all the scientific issues regarding each concept. However, the decades \u2013 long delays in realizing fusion for power production caused some of these efforts to shift recently & noticeably to the\ncommercial arena where a literal accountability of the progress of these projects is conducted. This status review paper gives a quick historical background on nuclear fusion science & technologies, explains briefly a few innovative nuclear fusion energy production methods with a focus on the rapidly growing commercial trend of nuclear fusion research and developments efforts.",
"URL": "NaN",
"title": "Status of nuclear fusion energy science & technology for power production: progress & prospects",
"year_published": 2022,
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"abstract": "We present the design parameters of a diode-pumped 100J-class multi-slab Yb:YAG laser at 10 Hz scalable to the kJ\r\nregime. Results of detailed energetics and thermo-optical modeling confirm the viability of cryogenic helium-gas cooling approach to drastically reduce thermally-induced distortions in the laser slabs. In addition, a comparison of spectral measurements from laser-diode stacks and Yb:YAG crystals validates the feasibility of highly efficient diode-pumped solid-state lasers at cryogenic temperatures.",
"URL": "http://ui.adsabs.harvard.edu/abs/2013SPIE.8602E..08L/abstract",
"title": "HiLASE cryogenically-cooled diode-pumped laser prototype for inertial fusion energy",
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"URL": "http://www.basko.net/mm/ppaps/NF2005_45_10_S291Sharkov.pdf",
"title": "Power plant design and accelerator technology for heavy ion inertial fusion energy",
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"abstract": "High-temperature superconductors (HTS) are considered as a competitive candidate to be used for the heliotron-type fusion energy reactor FFHR. In order to confirm the bending strain behavior of large-scale HTS conductors, degradation of critical currents by bending strain has been examined in liquid nitrogen (at 77 K) for several samples. The experiment started with two types of reduced-scale conductors with four YBCO tapes, one with copper and YBCO tapes distributed uniformly (Type-A) and the other with YBCO concentrated at the center (Type-B). In order to reconstruct the obtained results, another series of experiment were done by bending a single YBCO tape in two forms: soldered on to a single copper tape and embedded in a copper jacket. We found that even the bending strain of 0.5% defined for the whole conductor thickness should not be a problem from the viewpoint of critical current degradation if we adopt Type-B design with HTS tapes located at the center of the conductor.",
"URL": "https://ieeexplore.ieee.org/document/5433286/",
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"abstract": "A brief description of plasma, its types and fundamental requirements necessary to study the physics of plasma has been presented through this article. Information given here would be useful to those who have the basic knowledge of physics. Mathematical complications have been avoided to suit the purpose. Varied applications of plasma have been introduced. A little detail has been devoted to one of the major applications of plasma physics known as theoretical thermonuclear fusion studies. Physics of inertial confinement together with the role of self-generated magnetic field in the design of fusion targets have also been described.\r\n\r\n Himalayan Journal of Sciences 1(1): 21-24, 2003",
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"abstract": "Development of inertial fusion energy (IFE) will require continued R&D in target physics, driver technology, target production and delivery systems, and chamber technologies. It will also require the integration of these technologies in tests and engineering demonstrations of increasing capability and complexity. Development needs in each of these areas are discussed. It is shown how IFE development will leverage off the DOE Defense Programs funded inertial confinement fusion (ICF) work.",
"URL": "https://ans.org/pubs/journals/fst/a_42985",
"title": "Developing inertial fusion energy - Where do we go from here?",
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"abstract": "Nuclear proliferation risks from magnetic fusion energy associated with access to weapon-usable materials can be divided into three main categories: (1) clandestine production of weapon-usable material in an undeclared facility, (2) covert production of such material inn a declared facility, and (3) use of a declared facility in a breakout scenario, in which a state begins production of fissile material without concealing the effort. In this paper we address each of these categories of risks from fusion. For each case, we find that the proliferation risk from fusion systems can be much lower than the equivalent risk from fission systems, if the fusion system is designed to accommodate appropriate safeguards.",
"URL": "http://web.mit.edu/fusion-fission/HybridsPubli/Goldston_Fusion_Proliferation.pdf",
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"abstract": "One of the most advanced fast ignition programmes is the fast ignition realization experiment (FIREX). The goal of its first phase is to demonstrate ignition temperature of 5\u00a0keV, followed by the second phase to demonstrate ignition-and-burn. The second series experiment of FIREX-I, from late 2010 to early 2011, has demonstrated a high (>10%) coupling efficiency from laser to thermal energy of the compressed core, suggesting that the ignition temperature can be achieved at laser energy below 10\u00a0kJ. Further improvement of the coupling efficiency is expected by introducing laser-driven magnetic fields.",
"URL": "http://iopscience.iop.org/article/10.1088/0029-5515/53/10/104021/meta",
"title": "Present status of fast ignition realization experiment and inertial fusion energy development",
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"abstract": "The essential physical phenomena that will occur in Inertial Fusion Energy (IFE) reactors can be studied in a facility where the driver energy and target yield are reduced. The Integrated Test Facility (ITF) will study reactor relevant phenomena affecting drivers, beam transport, targets, and target chambers. The target chambers for reactors and the ITF could be designed using any one of several target chamber concepts. This paper involves the comparison, with computer simulation, of the phenomena occurring in the target chambers of three power reactor concepts (OSIRIS, HYLIFE-II, and CASCADE) with that occurring in ITF target chambers using the same design concept.",
"URL": "https://www.ans.org/pubs/journals/fst/a_40265",
"title": "Parametric target chamber simulations for the Inertial Fusion Energy Integrated Test Facility",
"year_published": 1994,
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"abstract": "High-enery, rep.-rated, diode-pumped solid-state laser (DPSSL) is one of leading candidates for inertial fusion energy driver (IFE) and related laser-driven high-field applications. The project for the development of IFE laser driver in Japan, HALNA (High Average-power Laser for Nuclear Fusion Application) at ILE, Osaka University, aims to demonstrate 100-J pulse energy at 10 Hz rep. rate with 5 times diffraction limited beam quality. In this article, the advanced solid-state laser technologies for one half scale of HALNA (50J, 10 Hz) are presented including thermally managed slab amplifier of Nd:phosphate glass and zig-zag optical geometry, and uniform, large-area diode-pumping.",
"URL": "https://jp4.journaldephysique.org/articles/jp4/abs/2006/02/jp4133122/jp4133122.html",
"title": "The HALNA project : Diode-pumped solid-state laser for inertial fusion energy",
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"abstract": "The attainment of economic, safe fusion power has been described as the most sophisticated scientific problem ever attacked by mankind. The goal of the magnetic fusion program is to develop and demonstrate pure fusion central electric power stations for commercial applications. Neutral beam heating systems are a basic component of the tokamak and mirror experimental fusion plasma confinement devices. The development and application of multimegawatt neutral beam heating systems for PLT, PDX, ISX, TFTR, Doublet-III and MFTF experiments and a plan for developing higher power, longer pulse length, more efficient systems for future application is presented.",
"URL": "https://ui.adsabs.harvard.edu/abs/1979ITNS...26.1266S/abstract",
"title": "Neutral Beam Injectors for the Magnetic Fusion Energy Program: Progress and Prognosis for the Future",
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"abstract": "The ARIES Team currently is engaged in an effort called the \u201cARIES Pathways Study\u201d. The goals of this study are to evaluate remaining R&D needs toward practical fusion energy and to identify and ev...",
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"title": "An Evaluation of Fusion Energy R&D Gaps Using Technology Readiness Levels",
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"abstract": "High current density cables are needed for the engineering design of potentially low cost, simpler geometry high temperature superconducting (HTS) magnets in the promising magnetic configurations as a fusion pilot plant (FPP) option. Significant technology maturation efforts are underway by privately funded startups with the goal to demonstrate mature HTS magnet technology. Test results, however, indicate critical engineering issues remain to be addressed to meet performance goals, and demonstrate HTS coil operation repeatability and reliability. To this end, exploring and enabling multiple viable conductor and cable options is vital. Partnering with a private fusion startup and manufacturers of superconducting strands and cables, Princeton Plasma Physics Laboratory (PPPL) is exploring and seeking to de-risk the aggressive high field approach presently targeted by others. Our main objective is to develop, test and calibrate novel high current density cables for a broad deployment of affordable and reliable coils using Bi-2212 conductors. If successful, such a project will provide technical feasibility for promising FPP configurations including spherical tokamaks (ST) and compact stellarators. We aim at the state-of-the-art Bi-2212 cable technologies toward a current density of 100 A/mm2 at 16 T and 4.2 K-10 K operation for low cost, simpler geometry toroidal field (TF) coils for compact stellarators developed by fusion startup companies on a timeline consistent with the FPP initiatives and beyond.",
"URL": "NaN",
"title": "High Current Density Cables for Simpler HTS Magnets in Fusion Energy Systems",
"year_published": 2024,
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"sentence": "Our main objective is to develop, test and calibrate novel high current density cables for a broad deployment of affordable and reliable coils using Bi-2212 conductors.",
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"sentence": "We aim at the state-of-the-art Bi-2212 cable technologies toward a current density of 100 Amm2 at 16 T and 4.2 K-10 K operation for low cost, simpler geometry toroidal field TF coils for compact stellarators developed by fusion startup companies on a timeline consistent with the FPP initiatives and beyond.",
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"abstract": "An overview of the present status of development of a hollow foam shell designed to produce high yields when used in a krypton fluoride inertial fusion energy (IFE) reactor is presented. Prototype ...",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST43-321",
"title": "Development of Divinylbenzene Foam Shells for Use as Inertial Fusion Energy Reactor Targets",
"year_published": 2003,
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"Nuclear engineering",
"Nanotechnology",
"Inertial frame of reference",
"Materials science",
"Fusion power",
"Divinylbenzene",
"Shell (structure)",
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"first_author": "Jon Streit",
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"abstract": "NIF is being configured so as to not preclude conduct of radiation experiments that will contribute to evaluating the readiness of military systems and components to withstand radiation environments. The range of possible experimental environments and the flexibility to introduce various types of experimental packages suggests synergism with experiments related to Inertial Fusion Energy development on NIF. Design status of NIF features to support radiation experiments is described, and a relationship to their applicability to IFE experimentation on NIF is discussed.",
"URL": "http://www.osti.gov/scitech/biblio/379040-utility-national-ignition-facility-inertial-fusion-energy-radiation-sciences-experiments",
"title": "Utility of the National Ignition Facility for inertial fusion energy and radiation sciences experiments",
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"abstract": "This paper reports on the design of the thermal energy conversion system for the Prometheus-L inertial fusion energy power plant, emphasizing features affected by characteristics of the fusion ther...",
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"abstract": "An overview is given of recent experimental results in the areas of innovative confinement concepts, operational scenarios and confinement experiments as presented at the 2010 IAEA Fusion Energy Conference. Important new findings are presented from fusion devices worldwide, with a strong focus towards the scientific and technical issues associated with ITER and W7-X devices, presently under construction.",
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"abstract": "Well-coordinated international fusion materials research on multiple fundamental feasibility issues can serve an important role during the next ten years. Due to differences in national timelines and fusion device concepts, a parallel-track (multimodal) approach is currently being used for developing fusion energy. An overview is given of the current state-of-the-art of major candidate materials systems for next-step fusion reactors, including a summary of existing knowledge regarding operating temperature and neutron irradiation fluence limits due to high-temperature strength and radiation damage considerations, coolant compatibility information, and current industrial manufacturing capabilities. There are two inter-related overarching objectives of fusion materials research to be performed in the next decade: (1) understanding materials science phenomena in the demanding DT fusion energy environment, and (2) application of this knowledge to develop and qualify materials to provide the basis for next-step facility construction authorization by funding agencies and public safety licensing authorities. The critical issues and prospects for development of high-performance fusion materials are discussed along with recent research results and planned activities of the international materials research community.",
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"abstract": "The principles of laser fusion are the implosion of fuel pellets and the inertial confinement of fusion plasma produced by implosion. The process contains a lot of interesting physics, some of which is related to other newly developing fields such as astrophysics, hydrodynamics with radiation and turbulence, nonequilibrium atomic physics, and material science of extreme conditions. This, therefore, opens up new research fields and methods in basic science. On the other hand, fusion research aims at energy development for the future. The state of the art of inertial confinement fusion has reached a level where a goal-oriented program could be arranged for physics investigations and also technological developments.",
"URL": "https://iopscience.iop.org/article/10.1088/0034-4885/59/9/002",
"title": "PRINCIPLES OF INERTIAL CONFINEMENT FUSION : PHYSICS OF IMPLOSION AND THE CONCEPT OF INERTIAL FUSION ENERGY",
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"Statistical physics",
"Aerospace engineering",
"Radiation",
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"Inertial frame of reference",
"Implosion",
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"first_author": "S. Nakai",
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"abstract": "The present study reveals forthcoming break-even conditions of tokamak plasma performance for the fusion energy development. The first condition is the electric break-even condition, which means that the gross electric power generation is equal to the circulating power in a power plant. This is required for fusion energy to be recognized as a suitable candidate for an alternative energy source. As for the plasma performance (normalized beta value \u0392N), confinement improvement factor for H-mode HH, the ratio of plasma density to Greenwald density fnGW), the electric break-even condition requires the simultaneous achievement of 1.2 < \u0392N < 2.7, 0.8 < HH, and 0.3 < fnGW < 1.1 under the conditions of a maximum magnetic field on the TF coil Btmax = 16 T, thermal efficiency \u03b7e = 30 %, and current drive power PNBI < 200 MW. It should be noted that the relatively moderate conditions of \u0392N \u02dc 1.8, HH \u02dc 1.0, and fnGW \u02dc 0.9, which correspond to the ITER reference operation parameters, have a strong potential to achieve the electric break-even condition. The second condition is the economic break-even condition, which is required for fusion energy to be selected as an alternative energy source in the energy market. By using a long-term world energy scenario, a break-even price for introduction of fusion energy in the year 2050 is estimated to lie between 65 mill/kWh and 135 mill/kWh under the constraint of 550 ppm CO2 concentration in the atmosphere. In the present study, this break-even price is applied to the economic break-even condition. However, because this break-even price is based on the present energy scenario including uncertainties, the economic break-even condition discussed here should not be considered the sufficient condition, but a necessary condition. Under the conditions of Btmax = 16 T, \u03b7e = 40 %, plant availability 60 %, and a radial build with/without CS coil, the economic break-even condition requires \u0392N \u02dc 5.0 for 65 mill/kWh of lower break-even price case. Finally, the present study reveals that the demonstration of steady-state operation with \u0392N \u02dc 3.0 in the ITER project leads to the upper region of the break-even price in the present world energy scenario, which implies that it is necessary to improve the plasma performance beyond that of the ITER advanced plasma operation.",
"URL": "http://altmetrics.ceek.jp/article/ci.nii.ac.jp/naid/110006282095",
"title": "Forthcoming Break-Even Conditions of Tokamak Plasma Performance for Fusion Energy Development",
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"Nuclear engineering",
"Physics",
"Fusion power",
"Energy market",
"Beta (plasma physics)",
"Fusion energy gain factor",
"Electricity generation",
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"first_author": "Ryoji Hiwatari",
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"abstract": "An innovative gas compression system is proposed and computationally researched to achieve a short time response as needed in engineering applications such as hydrogen fusion energy reactors and high speed hammers. The system consists of a reservoir containing high pressure gas connected to a straight tube which in turn is connected to a spherical duct, where at the sphere's centre plasma resides in the case of a fusion reactor. Diaphragm located inside the straight tube separates the reservoir's high pressure gas from the rest of the plenum. Once the diaphragm is breached the high pressure gas enters the plenum to drive pistons located on the inner wall of the spherical duct that will eventually end compressing the plasma. Quasi-1D and axisymmetric flow formulations are used to design and analyse the flow dynamics. A spike is designed for the interface between the straight tube and the spherical duct to provide a smooth geometry transition for the flow. Flow simulations show high supersonic flow hitting the end of the spherical duct, generating a return shock wave propagating upstream and raising the pressure above the reservoir pressure as in the hammer wave problem, potentially giving temporary pressure boost to the pistons. Good agreement is revealed between the two flow formulations pointing to the usefulness of the quasi-1D formulation as a rapid solver. Nevertheless, a mild time delay in the axisymmetric flow simulation occurred due to moderate two-dimensionality effects. The compression system is settled down in a few milliseconds for a spherical duct of 0.8 m diameter using Helium gas and a uniform duct cross-section area. Various system geometries are analysed using instantaneous and time history flow plots.",
"URL": "https://qmro.qmul.ac.uk/xmlui/handle/123456789/23265",
"title": "Flow design and simulation of a gas compression system for hydrogen fusion energy production",
"year_published": 2017,
"fields_of_study": [
"Gas compressor",
"Hammer",
"Materials science",
"Choked flow",
"Duct (flow)",
"Fusion power",
"Plenum space",
"Mechanics",
"Shock wave",
"Plasma",
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"first_author": "Eldad Avital",
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"sentence": "Once the diaphragm is breached the high pressure gas enters the plenum to drive pistons located on the inner wall of the spherical duct that will eventually end compressing the plasma.",
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"sentence": "Quasi-1D and axisymmetric flow formulations are used to design and analyse the flow dynamics.",
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"abstract": "The latest generations of rare-earth substituted and nano-doped YBa2Cu3O7-x (YBCO) high temperature superconductors (HTS) developed for applications in magnetic fields are being evaluated for poten...",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST13-735",
"title": "Irradiation Response of Next Generation High Temperature Superconductors for Fusion Energy Applications",
"year_published": 2014,
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"abstract": "Liquids may be used between the magnetic confined fusion plasma and the first wall of the plasma chamber to reduce the material damage through displacements per atom (dpa) and helium gas production...",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST98-A56",
"title": "Neutronic Calculations for a Magnetic Fusion Energy Reactor with Liquid Protection for the First Wall",
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"Energy (signal processing)",
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"abstract": "To best utilize the built-in helical divertors in the heliotron-type fusion energy reactor, we propose a new divertor sweeping scheme that reduces both the divertor heat flux and erosion of the divertor plates. This scheme employs a small set of helical coils, which we term helical divertor coils. The divertor legs can be moved by modulating the current amplitude of helical divertor coils by a few per cent of the current amplitude of the main helical coils. Despite the movement of the divertor legs, this scheme changes the magnetic surfaces very little. The strike point width is increased to ~800?mm and rapid sweeping reduces the time-averaged heat flux to a <1?MW?m?2 level with a total power flow of ~600?MW to the divertor regions for a fusion power of 3?GW. Divertor plate erosion is reduced, enabling the replacement cycle to be significantly prolonged. We propose that the helical divertor coils be fabricated using YBCO high-temperature superconductors and be constructed in prefabricated segments that are joined on site.",
"URL": "http://iopscience.iop.org/article/10.1088/0029-5515/51/10/103017/pdf",
"title": "Heat flux reduction by helical divertor coils in the heliotron fusion energy reactor",
"year_published": 2011,
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"Nuclear engineering",
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"Materials science",
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{
"abstract": "The fusion energies of several oxide mixtures were obtained by measuring the total radiant energy emitted during the solidification period. Values obtained for 60BeO-40CaO, 48CaO-52Al2O3, 75CaO-25B2O3, and 80BeO-20Li2O (mole %) were, respectively, 200, 85, 160, and 110 cal/g.",
"URL": "https://scitation.aip.org/content/aip/journal/jap/33/11/10.1063/1.1931155",
"title": "Fusion Energies of 60BeO-40CaO, 48CaO-52Al2O3, 75CaO-25B2O3, and 80BeO-20Li2O",
"year_published": 1962,
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"Fusion",
"Inorganic chemistry",
"Materials science",
"Oxide",
"Qualitative analysis",
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"Thermal radiation",
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"abstract": "AbstractMaking fusion power viable both technologically and commercially has been a challenge for decades due to the great complexity of the science and engineering challenges. In recent years, changes in both government policies and the emergence of private fusion companies have ushered a newfound push to accelerate fusion energy development. Kyoto Fusioneering (KF) is a privately funded fusion engineering start-up, founded to accelerate the development of high performance, commercially viable technologies that will be required for a fusion power plant, specifically those associated with heating and current drive systems, power generation, and the tritium fuel cycle. The company is focused on supporting the rapid expansion of the budding fusion industry. This paper provides a high-level description of some of the technical and industrial challenges it is tackling in developing a commercial fusion reactor, in particular in relation to: plasma heating with gyrotrons, tritium handling and breeding, energy conversion, and fusion materials. It provides an overview of KF's activities in finding solutions to challenges in each of these areas, including via its new testing facility now under construction, UNITY (Unique Integrated Testing Facility). KF\u2019s core capabilities and areas of R&D focus are discussed, with reference to how they benefit the development of a new fusion industry as a whole and bring the technology closer to industrialisation, including via UNITY and through collaboration with external partners. The importance of industrialisation and subsequently commercialisation is also discussed, through KF\u2019s assessment of the newly emerging fusion ecosystem, and where KF as a company sits within it.",
"URL": "https://link.springer.com/content/pdf/10.1007/s10894-023-00346-y.pdf",
"title": "Kyoto Fusioneering's Mission to Accelerate Fusion Energy: Technologies, Challenges and Role in Industrialisation",
"year_published": 2023,
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"abstract": "The Lawson criterion is a key concept in the pursuit of fusion energy, relating the fuel density $n$, (energy) confinement time $\\tau$, and fuel temperature $T$ to the energy gain $Q$ of a fusion plasma. The purpose of this paper is to explain and review the Lawson criterion and to provide a compilation of achieved parameters for a broad range of historical and contemporary fusion experiments. Although this paper focuses on the Lawson criterion, it is only one of many equally important factors in assessing the progress and ultimate likelihood of any fusion concept becoming a commercially viable fusion energy system. Only experimentally measured or inferred values of $n$, $\\tau$, and $T$ that have been published in the peer-reviewed literature are included in this paper. For extracting these parameters, we discuss methodologies that are necessarily specific to different fusion approaches (including magnetic, inertial, and magneto-inertial fusion). This paper is intended to serve as a reference for fusion researchers and a tutorial for all others interested in fusion energy.",
"URL": "https://meetings.aps.org/Meeting/DPP21/Session/PT02.1",
"title": "Progress toward Fusion Energy Breakeven and Gain as Measured against the Lawson Criterion",
"year_published": 2021,
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"abstract": "We have begun building the ''Mercury'' laser system as the first in a series of new generation diode-pumped solid-state lasers for inertial fusion research. Mercury will integrate three key technologies: diodes, crystals, and gas cooling, within a unique laser architecture that is scalable to kilojoule and megajoule energy levels for fusion energy applications. The primary near-term performance goals include 10% electrical efficiencies at 10 Hz and 1005 with a 2-10 ns pulse length at 1.047 {micro}m wavelength. When completed, Mercury will allow rep-rated target experiments with multiple chambers for high energy density physics research.",
"URL": "https://ui.adsabs.harvard.edu/abs/2000SPIE.3886...57B/abstract",
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"entity": "Mercury"
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{
"category": "Experimental Apparatus",
"entity": "Diodes"
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"category": "Experimental Apparatus",
"entity": "Crystals"
},
{
"category": "Experimental Apparatus",
"entity": "Gas cooling"
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{
"sentence": "The primary near-term performance goals include 10 electrical efficiencies at 10 Hz and 1005 with a 2-10 ns pulse length at 1.047 wavelength.",
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"category": "Physics Entity",
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"sentence": "When completed, Mercury will allow rep-rated target experiments with multiple chambers for high energy density physics research.",
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"category": "Experimental Apparatus",
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{
"abstract": "A concept for a new fusion-fission hybrid technology is being developed at Lawrence Livermore National Laboratory. The primary application of this technology is base-load electrical power generation. However, variants of the baseline technology can be used to \"burn\" spent nuclear fuel from light water reactors or to perform selective transmutation of problematic fission products. The use of a fusion driver allows very high burn-up of the fission fuel, limited only by the radiation resistance of the fuel form and system structures. As a part of this process, integrated process models have been developed to aid in concept definition. Several models have been developed. A cost scaling model allows quick assessment of design changes or technology improvements on cost of electricity. System design models are being used to better understand system interactions and to do design trade-off and optimization studies. Here we describe the different systems models and present systems analysis results. Different market entry strategies are discussed along with potential benefits to US energy security and nuclear waste disposal. Advanced technology options are evaluated and potential benefits from additional R&D targeted at the different options is quantified.",
"URL": "https://inis.iaea.org/Search/search.aspx?orig_q=RN:42051281",
"title": "Integrated process modeling for the laser inertial fusion Energy (LIFE) generation system",
"year_published": 2010,
"fields_of_study": [
"Nuclear engineering",
"Engineering",
"Systems engineering",
"Laser Inertial Fusion Energy",
"Burnup",
"Energy source",
"Systems design",
"Electricity generation",
"Cost of electricity by source",
"Spent nuclear fuel",
"Radioactive waste"
],
"first_author": "Wayne R. Meier",
"scholarly_citations_count": 5,
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"sentence": "The use of a fusion driver allows very high burn-up of the fission fuel, limited only by the radiation resistance of the fuel form and system structures.",
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"sentence": "As a part of this process, integrated process models have been developed to aid in concept definition.",
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"sentence": "Several models have been developed.",
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"sentence": "A cost scaling model allows quick assessment of design changes or technology improvements on cost of electricity.",
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"category": "Theory and Calculation",
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"sentence": "System design models are being used to better understand system interactions and to do design trade-off and optimization studies.",
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"sentence": "Here we describe the different systems models and present systems analysis results.",
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"sentence": "Different market entry strategies are discussed along with potential benefits to US energy security and nuclear waste disposal.",
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"sentence": "Advanced technology options are evaluated and potential benefits from additional RD targeted at the different options is quantified.",
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{
"abstract": "Here we report recent progress for the fast ignition inertial confinement fusion demonstration. The fraction of low energy ( 4% of the heating efficiency and > 4 keV of ion temperature are achievable by using GEKKO-XII and LFEX, properly designed cone-fuel and an external magnetic field.",
"URL": "http://iopscience.iop.org/article/10.1088/1742-6596/717/1/012006/pdf",
"title": "The status of Fast Ignition Realization Experiment (FIREX) and prospects for inertial fusion energy",
"year_published": 2016,
"fields_of_study": [
"Inertial confinement fusion",
"Magnetic field",
"Nuclear engineering",
"Physics",
"Ignition system",
"Inertial frame of reference",
"Atomic physics",
"Fusion power",
"Low energy",
"Heating efficiency",
"Realization (systems)"
],
"first_author": "H. Azechi",
"scholarly_citations_count": "NaN",
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"sentence": "The fraction of low energy 4 of the heating efficiency and 4 keV of ion temperature are achievable by using GEKKO-XII and LFEX, properly designed cone-fuel and an external magnetic field.",
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{
"abstract": "Nuclear fusion is receiving tremendous global interest due to its promise as a source of clean and abundant energy. Although scientific breakeven was recently demonstrated via inertial confinement fusion, economic breakeven has not yet been achieved in any form of fusion. A key barrier for economic viability is the high cost of fabricating the fuel containers (i.e., the targets). Here, we present a quantitative framework and apply it to generate a target manufacturing technology development roadmap to enable economically viable inertial fusion energy. We examine the impact of our recent work in nanoscale additive manufacturing (i.e., 3D printing) and identify the next steps toward economically viable fusion energy. Our analysis has implications for manufacturing technology developers, fusion power plant designers, funding agencies, and policy makers. It demonstrates that economic target manufacturing cannot be achieved by merely increasing the industrial capacity; instead, novel affordable manufacturing technologies must be developed.",
"URL": "NaN",
"title": "Additively manufactured nanoporous foam targets for economically viable inertial fusion energy",
"year_published": 2024,
"fields_of_study": [
"Fusion power",
"Inertial confinement fusion",
"Nanoporous",
"Key (lock)",
"Fusion",
"Manufacturing engineering",
"3D printing",
"Process engineering",
"Computer science",
"Business",
"Nanotechnology",
"Engineering",
"Mechanical engineering",
"Materials science",
"Linguistics",
"Philosophy",
"Physics",
"Plasma",
"Computer security",
"Quantum mechanics"
],
"first_author": "Sourabh K. Saha",
"scholarly_citations_count": "NaN",
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"sentence": "Although scientific breakeven was recently demonstrated via inertial confinement fusion, economic breakeven has not yet been achieved in any form of fusion.",
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"category": "Concept",
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"sentence": "A key barrier for economic viability is the high cost of fabricating the fuel containers .., the targets.",
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"sentence": "Here, we present a quantitative framework and apply it to generate a target manufacturing technology development roadmap to enable economically viable inertial fusion energy.",
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"sentence": "We examine the impact of our recent work in nanoscale additive manufacturing .., 3D printing and identify the next steps toward economically viable fusion energy.",
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{
"sentence": "Our analysis has implications for manufacturing technology developers, fusion power plant designers, funding agencies, and policy makers.",
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"category": "Facility or Institution",
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"category": "Facility or Institution",
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"category": "Person",
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{
"sentence": "It demonstrates that economic target manufacturing cannot be achieved by merely increasing the industrial capacity instead, novel affordable manufacturing technologies must be developed.",
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},
{
"abstract": "Based on the theory of continuous wavelet transform and information entropy,a new criterion:fusion energy scale entropy was put forward to monitor the stability of rotary machinery. Analysis of testing data and comparing with single channel demonstrate that the proposed criterion can well reveal the stability of rotary machinery at each scale; furthermore it can also provide numerical data of stability for condition monitoring and fault diagnosis or rotary machinery.",
"URL": "http://en.cnki.com.cn/Article_en/CJFDTOTAL-JXQD201001007.htm",
"title": "FUSION ENERGY SCALE ENTROPY AND ITS APPLICATION IN STABILITY IDAGNOSIS OF ROTARY MACHINERY",
"year_published": 2010,
"fields_of_study": [
"Engineering",
"Control engineering",
"Test data",
"Fusion power",
"Condition monitoring",
"Control theory",
"Entropy (information theory)",
"Continuous wavelet transform"
],
"first_author": "Dong Xin",
"scholarly_citations_count": "NaN",
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"sentence": "Based on the theory of continuous wavelet transform and information entropy,a new criterionfusion energy scale entropy was put forward to monitor the stability of rotary machinery.",
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"sentence": "Analysis of testing data and comparing with single channel demonstrate that the proposed criterion can well reveal the stability of rotary machinery at each scale furthermore it can also provide numerical data of stability for condition monitoring and fault diagnosis or rotary machinery.",
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}
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},
{
"abstract": "AbstractCommercial tritium resources available are too scarce to fully supply the future fusion reactors after International Thermonuclear Experimental Reactor (ITER). Tritium self\u2010sufficiency, ITER fails to fully validate, was regarded as one of the most important issues needed to be solved in the pathway of achieving fusion energy. After ITER, several concepts of fusion engineering test reactors and fusion demonstration reactors have been proposed worldwide, for example, Chinese Fusion Engineering Test Reactor (CFETR), Fusion Nuclear Science Facility (FNSF), DEMOnstration fusion reactor (DEMO) in European Union and Korea. CFETR is in the engineering design phase and would be hopefully completed around 2020. Tritium resources for the reactor start\u2010up and tritium self\u2010sufficiency are two primary issues besides the steady\u2010state operation for CFETR. The objectives of this work are as follows: (a) to introduce the preliminary fuel cycle concept and available tritium resources for CFETR, (b) to evaluate and discuss the tritium demand for CFETR start\u2010up (phase I: 200 MW) and the feasibility of DD start\u2010up, (c) to identify the possible pathways to tritium self\u2010sufficiency through sensitivity analysis based on the design baseline of CFETR, (d) to evaluate the consequences in case of failing tritium self\u2010sufficiency, and (e) to identify future R&D needed for tritium self\u2010sufficiency. It is expected to give insights into the question on how to start the reactor in a more economical way, into the feasibility of tritium self\u2010sufficiency, and into the question on what will happen in case of failing tritium self\u2010sufficiency.",
"URL": "https://onlinelibrary.wiley.com/doi/pdf/10.1002/ese3.291",
"title": "Insights into fuel start-up and self-sufficiency for fusion energy: The case of CFETR",
"year_published": 2019,
"fields_of_study": [
"Nuclear engineering",
"Fusion power",
"Start up",
"Fuel cycle",
"Computer science",
"Self-sufficiency"
],
"first_author": "Baojie Nie",
"scholarly_citations_count": 10,
"NER-RE": [
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"sentence": "AbstractCommercial tritium resources available are too scarce to fully supply the future fusion reactors after International Thermonuclear Experimental Reactor ITER.",
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"category": "Nuclear Fusion Experimental Facility",
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"sentence": "Tritium selfsufficiency, ITER fails to fully validate, was regarded as one of the most important issues needed to be solved in the pathway of achieving fusion energy.",
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"sentence": "After ITER, several concepts of fusion engineering test reactors and fusion demonstration reactors have been proposed worldwide, for example, Chinese Fusion Engineering Test Reactor CFETR, Fusion Nuclear Science Facility FNSF, DEMOnstration fusion reactor DEMO in European Union and Korea.",
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"category": "Nuclear Fusion Experimental Facility",
"entity": "ITER"
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"category": "Nuclear Fusion Experimental Facility",
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"category": "Nuclear Fusion Experimental Facility",
"entity": "FNSF"
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{
"category": "Nuclear Fusion Experimental Facility",
"entity": "DEMO"
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"category": "Country and location",
"entity": "European Union"
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"category": "Country and location",
"entity": "Korea"
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{
"category": "Country and location",
"entity": "China"
}
]
},
{
"sentence": "CFETR is in the engineering design phase and would be hopefully completed around 2020.",
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"category": "Time reference",
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"sentence": "Tritium resources for the reactor startup and tritium selfsufficiency are two primary issues besides the steadystate operation for CFETR.",
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"sentence": "The objectives of this work are as follows a to introduce the preliminary fuel cycle concept and available tritium resources for CFETR, to evaluate and discuss the tritium demand for CFETR startup phase I 200 MW and the feasibility of DD startup, to identify the possible pathways to tritium selfsufficiency through sensitivity analysis based on the design baseline of CFETR, to evaluate the consequences in case of failing tritium selfsufficiency, and to identify future RampD needed for tritium selfsufficiency.",
"entities": [
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"category": "Chemical Element or Compound",
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},
{
"sentence": "It is expected to give insights into the question on how to start the reactor in a more economical way, into the feasibility of tritium selfsufficiency, and into the question on what will happen in case of failing tritium selfsufficiency.",
"entities": [
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},
{
"abstract": "Configuration optimization is examined for the heliotron fusion energy reactor FFHR in order to find sufficient clearances between the ergodic region outside the nested magnetic surfaces and blankets at the inboard side of the torus. The standard configuration of FFHR, which is similar to that of LHD, has a relatively large major radius of the helical coils in order to satisfy this requirement. It has been found, as an alternative design, that equivalent clearances are obtained with a shorter major radius both by employing a lower helical pitch parameter and splitting the helical coils in the poloidal cross-section at the outboard side. Splitting the helical coils also provides another configuration that ensures magnetic well formation in the fairly large nested magnetic surfaces with outward shifted configurations. Optimization is being carried out for these configurations by adjusting the pitch modulation parameter to improve the particle confinement (\u00a9 2010 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim)",
"URL": "https://onlinelibrary.wiley.com/doi/pdf/10.1002/ctpp.200900030",
"title": "Configuration Studies on the Heliotron Fusion Energy Reactor with Split\u2010Type Helical Coils",
"year_published": 2010,
"fields_of_study": [
"Particle",
"Physics",
"Type (model theory)",
"Fusion power",
"Configuration optimization",
"Nuclear magnetic resonance",
"Modulation",
"Mechanics",
"Radius",
"Torus"
],
"first_author": "N. Yanagi",
"scholarly_citations_count": 1,
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"category": "Nuclear Fusion Device Type",
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"sentence": "Splitting the helical coils also provides another configuration that ensures magnetic well formation in the fairly large nested magnetic surfaces with outward shifted configurations.",
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"sentence": "Optimization is being carried out for these configurations by adjusting the pitch modulation parameter to improve the particle confinement 2010 WILEY-VCH Verlag GmbH Co. KGaA, Weinheim",
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]
},
{
"abstract": "Abstract We have begun building the Mercury laser system as the first in a series of new generation diode-pumped solid-state lasers for inertial fusion research. Mercury will integrate three key technologies: diodes, crystals and gas cooling, within a unique laser architecture that is scalable to kilojoules and megajoule energy levels for fusion energy applications. The primary near-term performance goals include 10% electrical efficiencies at 10 Hz and 100 J with a 2\u201310 ns pulse length at 1.047 \u03bc m wavelength. When completed, Mercury will allow rep-rated target experiments with multiple chambers for high energy density physics research.",
"URL": "https://ui.adsabs.harvard.edu/abs/2000CRASP...1..745B/abstract",
"title": "Mercury and Beyond: Diode-Pumped Solid-State Lasers for Inertial Fusion Energy",
"year_published": 2000,
"fields_of_study": [
"Optics",
"Fusion",
"Pulse duration",
"Materials science",
"Fusion power",
"Mercury laser",
"Laser",
"Mercury (element)",
"Wavelength",
"Diode"
],
"first_author": "Camille Bibeau",
"scholarly_citations_count": 3,
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"sentence": "Abstract We have begun building the Mercury laser system as the first in a series of new generation diode-pumped solid-state lasers for inertial fusion research.",
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"sentence": "Mercury will integrate three key technologies diodes, crystals and gas cooling, within a unique laser architecture that is scalable to kilojoules and megajoule energy levels for fusion energy applications.",
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"sentence": "The primary near-term performance goals include 10 electrical efficiencies at 10 Hz and 100 J with a 210 ns pulse length at 1.047 \u03bc wavelength.",
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},
{
"sentence": "When completed, Mercury will allow rep-rated target experiments with multiple chambers for high energy density physics research.",
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"category": "Nuclear Fusion Experimental Facility",
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"category": "Research field",
"entity": "high energy density physics"
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]
}
]
},
{
"abstract": "The high yield lithium injection fusion energy chamber with a tritium breeding ratio (TBR) of 1.75 is a prolific producer of excess tritium, which is currently considered a valuable commodity. Future safety, environmental, and political factors can, however, change this perception. In this paper, design modifications are discussed that can be used to control the TBR between 1.0 and 1.75. 11 refs.",
"URL": "http://www.osti.gov/scitech/biblio/5119505-tritium-breeding-management-high-yield-lithium-injection-fusion-energy-chamber",
"title": "Tritium breeding management in the high yield lithium injection fusion energy chamber",
"year_published": 1981,
"fields_of_study": [
"Nuclear engineering",
"Radiochemistry",
"Chemistry",
"Isotopes of lithium",
"Fusion power",
"Neutron irradiation",
"Tritium breeding ratio",
"Light nucleus",
"Lithium",
"Yield (chemistry)",
"Tritium"
],
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"abstract": "The Lawson criterion is a key concept in the pursuit of fusion energy, relating the fuel density n, pulse duration \u03c4 or energy confinement time \u03c4E, and fuel temperature T to the energy gain Q of a fusion plasma. The purpose of this paper is to explain and review the Lawson criterion and to provide a compilation of achieved parameters for a broad range of historical and contemporary fusion experiments. Although this paper focuses on the Lawson criterion, it is only one of many equally important factors in assessing the progress and ultimate likelihood of any fusion concept becoming a commercially viable fusion-energy system. Only experimentally measured or inferred values of n, \u03c4 or \u03c4E, and T that have been published in the peer-reviewed literature are included in this paper, unless noted otherwise. For extracting these parameters, we discuss methodologies that are necessarily specific to different fusion approaches (including magnetic, inertial, and magneto-inertial fusion). This paper is intended to serve as a reference for fusion researchers and a tutorial for all others interested in fusion energy.",
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"abstract": "Horizon 2020 is the largest EU Research and Innovation programme to date. The European fusion research programme for Horizon 2020 is outlined in the \u201cRoadmap to the realization of fusion energy\u201d and published in 2012 [1]. As part of it, the European Fusion Consortium (EUROfusion) has been established and will be responsible for implementing this roadmap through its members. The European fusion roadmap sets out a strategy for a collaboration to achieve the goal of generating fusion electricity by 2050. It is based on a goal-oriented approach with eight different missions including the development of heat-exhaust systems which must be capable of withstanding the large heat and particle fluxes of a fusion power plant (FPP). A summary of the main aims of the mission for a solution on heat-exhaust systems and the EUROfusion consortium strategy to set up an efficient Work Breakdown Structure and the collaborative efforts to address these challenges will be presented.",
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"title": "Correction to: A New Vision for Fusion Energy Research: Fusion Rocket Engines for Planetary Defense",
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"abstract": "Reduced-activation ferritic/martensitic (RAF/M) steels have been considered to be the prime candidate for the fusion blanket structural material. The irradiation data obtained up to now indicates rather high feasibility of the steels for application to fusion reactors because of their high resistance to degradation of material performance caused by both the irradiation-induced displacement damage and transmutation helium atoms. The martensitic structure of RAF/M steels consists of a large number of lattice defects before the irradiation, which strongly retards the formation of displacement damage through absorption and annihilation of the point defects generated by irradiation. Transmutation helium can be also trapped at those defects in the martensitic stricture so that the growth of helium bubbles at grain boundaries is suppressed. The major properties of the steels are well within our knowledge, and processing technologies are mostly developed for fusion application. RAF/M steels are now certainly ready to proceed to the next stage, that is, the construction of International Thermo-nuclear Experimental Reactor Test Blanket Modules (ITER-TBM). Oxide dispersion strengthening (ODS) steels have been developed for higher thermal efficiency of fusion power plants. Recent irradiation experiments indicated that the steels were quite highly resistant to neutron irradiation embrittlement, showing hardening accompanied by no loss of ductility. High-Cr ODS steels whose chromium concentration was in the range from 14 to 19 mass% showed high resistance to corrosion in supercritical pressurized water. It is shown that the 14Cr-ODS steel is susceptible to neither hydrogen nor helium embrittlement. A combined utilization of ODS steels with RAF/M steels will be effective to realize fusion power early at a reasonable thermal efficiency.",
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"abstract": "Controlled fusion energy from burning hydrogen with boron-11 is of interest because no neutrons are produced. Following the scheme of ignition by spherical irradiation by laser or particle beams, one has to deal with exorbitant conditions of densities and input energies. A new approach following the scheme of block ignition with laser pulses of picosecond (ps) duration and more than petawatt (PW) power led to the possibility of plane geometry irradiation of the fuel using the anomalous effect of block ignition for deuterium tritium (DT) based on updated conditions for the initial computations. We present the extension for H-11B resulting in a very less dramatic difference to DT than in the case of spherical pellet geometry. Ignition thresholds may be only about one order of magnitude higher and the needed temperatures of about 50\u00a0keV are no problem for the skin layer acceleration by nonlinear forces (SLANF) for the block generation.",
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"entity": "Hydrogen"
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"category": "Chemical Element or Compound",
"entity": "Boron-11"
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{
"sentence": "Following the scheme of ignition by spherical irradiation by laser or particle beams, one has to deal with exorbitant conditions of densities and input energies.",
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"category": "Experimental Apparatus",
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"sentence": "A new approach following the scheme of block ignition with laser pulses of picosecond ps duration and more than petawatt PW power led to the possibility of plane geometry irradiation of the fuel using the anomalous effect of block ignition for deuterium tritium DT based on updated conditions for the initial computations.",
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"sentence": "We present the extension for H-11B resulting in a very less dramatic difference to DT than in the case of spherical pellet geometry.",
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"sentence": "Ignition thresholds may be only about one order of magnitude higher and the needed temperatures of about 50 keV are no problem for the skin layer acceleration by nonlinear forces SLANF for the block generation.",
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"abstract": "An advanced tokamak is characterized by increased confinement, stability and steady state operation. The increased confinement and stability are obtained through modifications to the shape and profiles of the plasma and through stability feedback control. These modifications have to be self-consistent. The increased confinement makes it possible to make smaller and thereby lower cost reactors for the same power outpui as compared to conventional tokamaks. Four potential modes for advanced tokamaks are currently being studied on DIII-D: radiative improved mode, high internal inductance i mode, negative central shear (NCS) mode, and quiescent double barrier (QDB) mode.",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST01-A11963253",
"title": "Recent Findings in DIII\u2013D Relative to Advanced Tokamak Modes and their Implications for Fusion Energy",
"year_published": 2001,
"fields_of_study": [
"Tokamak",
"Atomic physics",
"Materials science",
"Fusion power",
"DIII-D",
"Computational physics",
"Steady state",
"Thermonuclear fusion",
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"first_author": "P. I. Petersen",
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{
"abstract": "Massive increases in energy demand are projected for countries such as China and India over this century e.g., many 100s of megawatts of electricity (MWe) of additional electrical capacity by 2050, with more additions later, are being considered for each of them. All energy sources will be required to meet such a demand. Fortunately, while world energy demand will be increasing, the world is well endowed with a variety of energy resources. However, their distribution does not match the areas of demand and there are many environmental issues. Such geopolitical issues affect China and India and make it important for them to be able to deploy improved technologies. In this regard, South Korea is an interesting example of a country that has developed the capability to do advanced technologies - such as nuclear power plants. International collaborations in developing these technologies, such as the International Thermonuclear Reactor (ITER), may be important in all energy areas. Fusion energy is viewed as an interesting potential option in these three countries.",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST05-A712",
"title": "Future World Energy Demand and Supply: China and India and the Potential Role of Fusion Energy",
"year_published": 2005,
"fields_of_study": [
"Renewable resource",
"Business",
"Natural resource economics",
"China",
"Geopolitics",
"Electricity",
"Energy source",
"Distribution (economics)",
"Nuclear power",
"Thermonuclear fusion"
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"first_author": "John Sheffield",
"scholarly_citations_count": 1,
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"abstract": "The Z-Pinch Power Plant (ZP-3) is the first concept to use the results at Sandia National Laboratories' Z accelerator in a power plant application. Assuming high-yield fusion pulses (of 1 to 20 GJ per shot at a rate of 0.1 Hz), we consider a unique shock and energy absorbing system to contain the energy. One concept answers the need for system standoff from the fusion reaction with a replaceable mechanical cartridge manufactured on-site. System studies suggest integrated blanket designs for absorbing the fusion energy, cartridge manufacture of recycled materials, and cartridge installation/replacement to maintain a reasonable duty cycle. An effective system design for ZP-3 requires an integrated blanket to shield the permanent structures from the high-energy neutron flux and strong shock wave, breed tritium, and simultaneously absorb the released fusion energy. We investigate the feasibility of this integrated blanket concept and explore the principles of a containment chamber-a crucible- and the containment mechanisms. An operational cycle is proposed to physically load hardware in 10-s intervals while maintaining operational conditions. Preliminary pressure and shock calculations demonstrate that highyield inertial fusion energy pulses can be contained if the appropriate energy-absorbing materials are used.",
"URL": "https://www.ans.org/pubs/journals/fst/a_290",
"title": "A Concept for Containing Inertial Fusion Energy Pulses in a Z-Pinch-Driven Power Plant",
"year_published": 2003,
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"Inertial confinement fusion",
"Nuclear engineering",
"Nuclear physics",
"Materials science",
"Duty cycle",
"Fusion power",
"Blanket",
"Z-pinch",
"Power station",
"Nuclear fusion",
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"first_author": "Gary E Rochau",
"scholarly_citations_count": 6,
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{
"abstract": "We are developing large pixel count, fast (\u2a7e100\u2002kHz) and continuously sampling soft x-ray (SXR) array for the diagnosis of magnetohydrodynamics (MHD) and turbulent fluctuations in magnetic fusion energy plasmas. The arrays are based on efficient scintillators, high thoughput multiclad fiber optics, and multichannel light amplification and integration. Compared to conventional x-ray diode arrays, such systems can provide vastly increased spatial coverage, and access to difficult locations with small neutron noise and damage. An eight-channel array has been built using columnar CsI:Tl as an SXR converter and a multianode photomultiplier tube as photoamplifier. The overall system efficiency is measured using laboratory SXR sources, while the time response and signal-to-noise performance have been evaluated by recording MHD activity from the spherical tori (ST) Current Drive Experiment-Upgrade and National Spherical Torus Experiment, both at Princeton Plasma Physics Laboratory.",
"URL": "https://www.vertilon.com/pdf/PP6218.pdf",
"title": "\u201cOptical\u201d soft x-ray arrays for fluctuation diagnostics in magnetic fusion energy experiments",
"year_published": 2004,
"fields_of_study": [
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"Optics",
"Physics",
"Scintillator",
"Optical fiber",
"Magnetohydrodynamics",
"Plasma diagnostics",
"Noise (electronics)",
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"first_author": "L. F. Delgado-Aparicio",
"scholarly_citations_count": 18,
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"abstract": "Abstract Previous studies of the safety and environmental aspects of the HYLIFE-II inertial fusion energy power plant design have used simplistic assumptions in order to estimate radioactivity releases under accident conditions. Conservatisms associated with these traditional analyses can mask the actual behavior of the plant and have revealed the need for more accurate modeling and analysis of accident conditions and radioactivity mobilization mechanisms. In the present work, computer codes traditionally used for magnetic fusion safety analyses (CHEMCON, MELCOR) have been applied for simulating accident conditions in a simple model of the HYLIFE-II IFE design. Here we consider a severe loss of coolant accident (LOCA) in conjunction with simultaneous failures of the beam tubes (providing a pathway for radioactivity release from the vacuum vessel towards the confinement) and of the two barriers surrounding the chamber (inner shielding and confinement building itself). Even though confinement failure would be a very unlikely event it would be needed in order to produce significant off-site doses. CHEMCON code allows calculation of long-term temperature transients in fusion reactor first wall, blanket, and shield structures resulting from decay heating. MELCOR is used to simulate a wide range of physical phenomena including thermal-hydraulics, heat transfer, aerosol physics and fusion product transport and release. The results of these calculations show that the estimated off-site dose is less than 5\u00a0mSv (0.5\u00a0rem), which is well below the value of 10\u00a0mSv (1\u00a0rem) given by the DOE Fusion Safety Standards for protection of the public from exposure to radiation during off-normal conditions.",
"URL": "https://www.sciencedirect.com/science/article/pii/S016890020100078X",
"title": "Accident consequences analysis of the HYLIFE-II inertial fusion energy power plant design",
"year_published": 2001,
"fields_of_study": [
"Inertial confinement fusion",
"Nuclear engineering",
"Physics",
"Electromagnetic shielding",
"Fusion power",
"MELCOR",
"Loss-of-coolant accident",
"Blanket",
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"first_author": "Susana Reyes",
"scholarly_citations_count": 10,
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{
"abstract": "AbstractDIII-D physics research addresses critical challenges for the operation of ITER and the next generation of fusion energy devices. This is done through a focus on innovations to provide solutions for high performance long pulse operation, coupled with fundamental plasma physics understanding and model validation, to drive scenario development by integrating high performance core and boundary plasmas. Substantial increases in off-axis current drive efficiency from an innovative top launch system for EC power, and in pressure broadening for Alfven eigenmode control from a co-/counter-Ipsteerable off-axis neutral beam, all improve the prospects for optimization of future long pulse/steady state high performance tokamak operation. Fundamental studies into the modes that drive the evolution of the pedestal pressure profile and electron vs ion heat flux validate predictive models of pedestal recovery after ELMs. Understanding the physics mechanisms of ELM control and density pumpout by 3D magnetic perturbation fields leads to confident predictions for ITER and future devices. Validated modeling of high-Zshattered pellet injection for disruption mitigation, runaway electron dissipation, and techniques for disruption prediction and avoidance including machine learning, give confidence in handling disruptivity for future devices. For the non-nuclear phase of ITER, two actuators are identified to lower the L\u2013H threshold power in hydrogen plasmas. With this physics understanding and suite of capabilities, a high poloidal beta optimized-core scenario with an internal transport barrier that projects nearly toQ= 10 in ITER at \u223c8 MA was coupled to a detached divertor, and a near super H-mode optimized-pedestal scenario with co-Ipbeam injection was coupled to a radiative divertor. The hybrid core scenario was achieved directly, without the need for anomalous current diffusion, using off-axis current drive actuators. Also, a controller to assess proximity to stability limits and regulate\u03b2Nin the ITER baseline scenario, based on plasma response to probing 3D fields, was demonstrated. Finally, innovative tokamak operation using a negative triangularity shape showed many attractive features for future pilot plant operation.",
"URL": "https://iopscience.iop.org/article/10.1088/1741-4326/ac2ff2",
"title": "DIII-D research advancing the physics basis for optimizing the tokamak approach to fusion energy",
"year_published": 2022,
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"Tokamak",
"Nuclear engineering",
"Physics",
"Basis (linear algebra)",
"Fusion power",
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"abstract": "A fusion power plant is described that utilizes a new version of the tandem mirror device including spinning liquid walls. The magnetic configuration is evaluated with an axisymmetric equilibrium code predicting an average beta of 60%. The geometry allows a flowing molten salt, (flibe-Li 2 BeF 4 ), which protects the walls and structures from damage arising from neutrons and plasma particles. The surface of the liquid facing the burning plasma is heated by bremsstrahlung radiation, line radiation, and by neutrons. The temperature of the free surface of the liquid is calculated, and then the evaporation rate is estimated from vapor-pressure data. The allowed impurity concentration in the burning plasma is taken as 1% fluorine, which gives a 17% reduction in the fusion power owing to D/T fuel dilution, with F line-radiation causing minor power degradation. The end leakage power density of 0.6 MW/m 2 is readily handled by liquid jets. The tritium breeding is adequate with natural lithium. The simple geometry and the use of liquid walls promise the cost of power competitive with that from fission and coal.",
"URL": "https://www.ans.org/pubs/journals/fst/a_1522",
"title": "Axisymmetric Tandem Mirror Magnetic Fusion Energy Power Plant with Thick Liquid-Walls",
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"Free surface",
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"Nuclear physics",
"Power density",
"Fusion power",
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"Beta (plasma physics)",
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"abstract": "Successful development of inertial fusion energy (IFE) requires that many technical issues be resolved. Separability of drivers, targets, chambers and other IFE power plant subsystems allows resolution of many of these issues in off-line facilities and programs. Periodically, major integrated facilities give a snapshot of the rate of progress toward the ultimate solutions. The National Ignition Facility (NIF) and Laser Megajoule (LMJ) are just such integrating facilities. This paper reviews the status of IFE development and projects what will be learned from the NIF and LMJ.",
"URL": "https://www.osti.gov/servlets/purl/791385/",
"title": "Inertial fusion energy development: what is needed and what will be learned at the National Ignition Facility",
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"Nanotechnology",
"Inertial frame of reference",
"Systems engineering",
"Fusion power",
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"Laser M\u00e9gajoule",
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"abstract": "We present experimental and theoretical studies of magnetic levitation of hydrogen gas bubble surrounded by liquid hydrogen confined in a semi-transparent spherical shell of 3 mm internal diameter. Such shells are used as targets for the inertial confinement fusion (ICF), for which a homogeneous (within a few percent) layer of a hydrogen isotope should be deposited on the internal walls of the shells. The gravity does not allow the hydrogen layer thickness to be homogeneous. To compensate this gravity effect, we have used a non-homogeneous magnetic field created by a 10 T superconductive solenoid. Our experiments show that the magnetic levitation homogenizes the thickness of liquid hydrogen layer. However, the variation of the layer thickness is very difficult to measure experimentally. Our theoretical model allows the exact shape of the layer to be predicted. The model takes into account the surface tension, gravity, van der Waals, and magnetic forces. The numerical calculation shows that the homogeneity of the layer thickness is satisfactory for the ICF purposes.",
"URL": "https://ui.adsabs.harvard.edu/abs/2002Cryo...42..253C/abstract",
"title": "Using magnetic levitation to produce cryogenic targets for inertial fusion energy: experiment and theory",
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"Fusion power",
"Liquid hydrogen",
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"abstract": "The focusing performance of a double magnetic lens and the delay in the arrival time at the shot point are presented for a Pb-coated superconducting inertial fusion energy target injection system. Magnets placed symmetrically in the injection path adjust the target trajectory and focus it toward the designated point. When the target passes through the magnetic lens, it receives deceleration and acceleration forces, producing a delay in the arrival time. c \u00a9 2009 The Japan Society of Plasma Science and Nuclear Fusion Research",
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"abstract": "Continuing improvements in electron linear accelerators, and associated targets, detectors, and data acquisition systems, make facilities based on these neutron sources very productive in meeting n...",
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"title": "Electron Linear Accelerators for Fast Neutron Data Measurements in Support of Fusion Energy Applications",
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"Neutron source",
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"abstract": "We propose cryogenic Yb:YAG ceramic as a novel reactor laser-driver material instead of conventional Nd:glass. Our research on cryogenic Yb:YAG revealed that both of stimulated emission cross section and thermal conductivity can be tuned well by controlling the material temperature. Using the obtained laser parameters in our experiments, a 1.3-MJ, 16-Hz diode-pumped laser system has been conceptually designed. The overall electrical-optical conversion efficiency is numerically calculated to be as high as 17%. The compact main amplifier with about 3000, m3 volume size would be realized by using the active mirror architecture. In addition, a 1-kJ laser system 'GENBU' has been designed as a milestone for the new driver.",
"URL": "https://ui.adsabs.harvard.edu/abs/2008JPhCS.112c2058K/abstract",
"title": "New concept for laser fusion energy driver by using cryogenically-cooled Yb:YAG ceramic",
"year_published": 2008,
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"Ceramic",
"Materials science",
"Amplifier",
"Energy conversion efficiency",
"Electronic engineering",
"Stimulated emission",
"Optoelectronics",
"Laser",
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"abstract": "The attractiveness of magnetic fusion as a commercial energy source will depend on its performance, relative to other energy technologies available in the same time frame, with respect to economics, environment, and safety. Although a variety of past and ongoing reviews of fusion's prospects touch different aspects of this issue, the Office of Fusion Energy (OFE) of the US Dept. of Energy is funding the work of a special national committee to pull together during FY 1986 a report emphasizing the interaction of environmental, safety, and economic characteristics in fusion reactor design and the prospects for achieving combinations of these characteristics that would make fusion an attractive long-term energy source compared to (or in symbiosis with) fission and other options.",
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"abstract": "Over the past 20 years, advances in tokamak physics and technology have prepared the field of magnetic confinement fusion research for the next step toward a steady-state burning plasma.",
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"abstract": "This year fusion ignition and gain are expected on the National Ignition Facility at LLNL. The pathway to inertial fusion\r\nenergy begins by addressing high average power operation of the diode pumped solid state laser system, target chamber,\r\ntarget injection and tracking, target mass production, blanket, and the balance of plant. To meet efficiency requirements,\r\nthe power conditioning for the laser diodes must be compact and efficient. A diode pulser has been designed to meet\r\nthese specifications, operate efficiently, and provide a means to minimizing cost and size for the estimated 4.4 million\r\npulsers needed for a power plant.",
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"abstract": "In inertial fusion energy (IFE) power plant designs, the fuel is a spherical layer of frozen DT contained in a target that is injected at high velocity into the reaction chamber. For direct drive, typically laser beams converge at the centre of the chamber (CC) to compress and heat the target to fusion conditions. To obtain the maximum energy yield from the fusion reaction, the frozen DT layer must be at about 18.5 K and the target must maintain a high degree of spherical symmetry and surface smoothness when it reaches the CC. During its transit in the chamber the cryogenic target is heated by radiation from the hot chamber wall. The target is also heated by convection as it passes through the rarefied fill-gas used to control chamber wall damage by x-rays and debris from the target explosion. This article addresses the temperature limits at the target surface beyond which target uniformity may be damaged. It concentrates on direct drive targets because fuel warm up during injection is not currently thought to be an issue for present indirect drive designs and chamber concepts. Detailed results of parametric radiative and convective heating calculations are presented for direct-drive targets during injection into a dry-wall reaction chamber. The baseline approach to target survival utilizes highly reflective targets along with a substantially lower chamber wall temperature and fill-gas pressure than previously assumed. Recently developed high-Z material coatings with high heat reflectivity are discussed and characterized. The article also presents alternate target protection methods that could be developed if targets with inherent survival features cannot be obtained within a reasonable time span.",
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{
"abstract": "The fertility rate for women and the related population growth rate for numerous developing (transitional) countries show a downward trend with increasing annual per capita energy use. On the assum...",
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"title": "World population and energy demand growth: the potential role of fusion energy in an efficient world",
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"abstract": "The advent of ultra-high power lasers allows laser power levels that are about 1000 times the power of all the power stations in the USA. This opens the way to new approaches for inertial confinement fusions (ICF) that in turn can drastically reduce the laser input energy needed to achieve practical ICF power. The specific approach discussed here involves inducing a fusion burn wave by laser-driven impact of a relatively large block of plasma on the outside of a solid density fusion target. This new method is specifically selected to enable the extremely attractive, but demanding, neutron-free proton\u2013B-11 fusion that potentially can lead to the long sought goal of an ultra \u201cclean\u201d fusion power plant.",
"URL": "http://newt.phys.unsw.edu.au/STAFF/VISITING_FELLOWS%26PROFESSORS/pdf/BlockEnergyEnvir.pdf",
"title": "Fusion energy without radioactivity: laser ignition of solid hydrogen\u2013boron (11) fuel",
"year_published": 2010,
"fields_of_study": [
"Inertial confinement fusion",
"Nuclear engineering",
"Electrical engineering",
"Engineering",
"Fusion",
"Laser power scaling",
"Fusion power",
"Laser ignition",
"Power station",
"Laser",
"Plasma"
],
"first_author": "Heinrich Hora",
"scholarly_citations_count": 82,
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"abstract": "The opportunities for international collaboration in fusion are discussed within the context of the present status of fusion development and international research and development activities. A spe...",
"URL": "https://www.tandfonline.com/doi/full/10.13182/FST82-A20793",
"title": "U.S. Strategy for International Collaboration on Magnetic Fusion Energy Development\u2014A Technological and Scientific View",
"year_published": 1982,
"fields_of_study": [
"Political science",
"Context (language use)",
"International research",
"Magnetic fusion",
"Energy development",
"Knowledge management"
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"first_author": "Weston M. Stacey",
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"abstract": "Proposed design of NIF is reviewed from the standpoint of radioactive and hazardous materials. Detailed analyses of these factors indicated that minimal environmental impacts are expected to occur, and very low exposures are predicted for both workers and the general public.",
"URL": "https://ans.org/pubs/journals/fst/a_43024",
"title": "The National Ignition Facility: Inertial Fusion Energy Applications, Waste Management and Environmental Impacts",
"year_published": 1996,
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"Nuclear decommissioning",
"Hazardous waste",
"Fusion power",
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"abstract": "AbstractProgress toward the successful completion of any program improves as the resources available to that program increase. International cooperation is a mechanism that can increase the resources available to the U.S. fusion program. Viewed historically as a science program, the progress in fusion R&D in the United States has been significantly enhanced through this mechanism. However, as fusion moves increasingly into engineering development toward commercial application, the benefits of science exchange may appear to be increasingly counterbalanced by (a) the potential increase in administrative costs and time delays and (b) the opportunity cost associated with sharing potentially proprietary technology information. The transition between fusion development phases (scientific to engineering) requires a reassessment and revamping of the scientific nonstrategy for international cooperation. The assessment of costs and benefits of previous mechanisms for international cooperation provides some fundamen...",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST82-A20792",
"title": "An Analysis of Potential Benefits To The United States from International Cooperation in Fusion Energy Development",
"year_published": 1982,
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"Risk analysis (engineering)",
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"Fusion power",
"Mechanism (sociology)",
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"abstract": "The contributions to the 22nd IAEA Fusion Energy Conference (FEC) in the categories of Fusion Technology (FT), ITER Activities (IT) and Safety and Economic Studies (SE) are reviewed. In the FT category, 68 papers were submitted, along with 57 papers submitted through the ITER Organisation in the IT category. Finally two papers were submitted in the SE category. The assembled body of work gave a good overview of the worldwide effort in fusion technology and particularly the prolific activity surrounding the ITER Design Review and the major progress with the ITER technology programme.",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/49/10/104002",
"title": "22nd IAEA Fusion Energy Conference: summary of contributions on Fusion Technology and ITER Activities",
"year_published": 2009,
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"abstract": "A target position measurement method using a compressed Arago spot image is presented for real time data processing. To decrease the amount of data of the Arago spot image, the image is optically compressed into a one dimensional line image by a cylindrical lens. The experimental results for a 5 mm diameter target demonstrated a measurement accuracy of 0.35 \u03bcm when the target was 10 m from a charge coupled device (CCD) camera.",
"URL": "https://www.jstage.jst.go.jp/article/pfr/4/0/4_0_S1012/_article",
"title": "Compression of Arago Spot Images for Rapid Position Measurement of Inertial Fusion Energy Targets",
"year_published": 2009,
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"Cylindrical lens",
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"abstract": "With the energy transformation, the traditional independent energy supply and consumption patterns can not fully meet the actual needs. In response to this situation and research needs, a multi-source fusion energy management and control system of multiple energy sources for regional energy internet is proposes and the system architecture, function design, and summarizes the key technologies involved in the system are Introduced in this paper. The system can realize various energy fusion and \"source-grid-load\" interaction in order to optimal scheduling management to various energy sources and the user.",
"URL": "https://www.dpi-proceedings.com/index.php/dtetr/article/download/15764/15275",
"title": "Research on Multi-Source Fusion Energy Management and Control System for Regional Energy Internet",
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"abstract": "Inertial fusion energy (IFE) targets injected into fusion chambers must withstand the demanding acceleration forces and the intense thermal environment of the fusion chamber. For indirect targets, ...",
"URL": "https://www.ans.org/pubs/journals/fst/a_36196",
"title": "Thermal and Structural Issues of Target Injection into a Laser-Driven Inertial Fusion Energy Chamber",
"year_published": 2014,
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"abstract": "Plate heat exchangers (PHEs) and double pipe heat exchangers (DPEs) are possible alternatives for gas-liquid heat transfer applications, particularly for relatively low heat duties of the order of few hundred Watt. One such application is cooling of the helium coolant gas used for heat removal from the first wall of tritium breeder blankets in fusion reactors, before the gas is purified. This work illustrates the selection of an optimal heat exchanger out of PHEs and DPEs for this application based on the total exchanger cost and floor space requirement. Heat transfer area requirements and pressure drop are predicted using appropriate Nusselt number and friction factor correlations. Preliminary cost estimations are made by considering the purchase cost of each unit and the cost of electrical energy required for fluid pumping. Thus the most economical PHE and DPE are identified. The PHE and DPE are then compared on the basis of space requirements. Effects of various design and operating parameters on the total cost of the optimal exchanger type have been evaluated. Heat exchanger effectiveness and exergy analyses have also been performed as part of the rating exercise for the optimal exchanger.",
"URL": "https://www.tsijournals.com/abstract/optimal-exchanger-selection-and-performance-analysis-for-heliumwater-heat-transfer-in-fusion-energy-applications-1764.html",
"title": "Optimal exchanger selection and performance analysis for heliumwater heat transfer in fusion energy applications",
"year_published": 2016,
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"abstract": "Parametric system studies of an inertial confinement fusion (ICF) reactor system to transmute fission products from a LWR economy have been carried out. The ICF reactors would produce net power in addition to transmuting fission products. The particular ICF concept examined is an impact fusion approach termed HYPERFUSE, in which hypervelocity pellets, traveling on the order of 100 to 300 km/sec, collide with each other or a target block in a reactor chamber and initiate a thermonuclear reaction. The DT fusion fuel is contained in a shell of the material to be transmuted, e.g., /sup 137/Cs, /sup 90/Sr, /sup 129/I, /sup 99/Tc, etc. The 14-MeV fusion neutrons released during the pellet burn cause transmutation reactions (e.g., (n,2n), (n,..cap alpha..), (n,..gamma..), etc.) that convert the long-lived fission products (FP's) either to stable products or to species that decay with a short half-life to a stable product. The transmutation parametric studies conclude that the design of the hypervelocity projectiles should emphasize the achievement of high densities in the transmutation regions (greater than the DT fusion fuel density), as well as the DT ignition and burn criterion (rho R = 1.0 to 3.0) requirements. These studies also indicate that masses on the ordermore\u00a0\u00bb of 1.0 g at densities of rho greater than or equal to 500.0 g/cm/sup 3/ are required for a practical fusion-based fission product transmutation system.\u00ab\u00a0less",
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"title": "HYPERFUSE: a hypervelocity inertial confinement system for fusion energy production and fission waste transmutation",
"year_published": 1981,
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"abstract": "Over the past several decades, significant and steady progress has been made in the development of fusion energy and its associated technology and in the understanding of the physics of high-temperature plasmas. While the demonstration of net fusion energy (fusion energy production exceeding that required to heat and confine the plasma) remains a task for the next millennia and while challenges remain, this progress has significantly increased confidence that the ultimate goal of societally acceptable (e.g. cost, safety, environmental considerations including waste disposal) central power production can be achieved. This progress has been shared by the two principal approaches to controlled thermonuclear fusion--magnetic confinement (MFE) and inertial confinement (ICF). ICF, the focus of this article, is complementary and symbiotic to MFE. As shown, ICF invokes spherical implosion of the fuel to achieve high density, pressures, and temperatures, inertially confining the plasma for times sufficient long (t {approx} 10{sup -10} sec) that {approx} 30% of the fuel undergoes thermonuclear fusion.",
"URL": "http://www.osti.gov/scitech/biblio/791695-national-ignition-facility-applications-inertial-fusion-energy-high-energy-density-science",
"title": "The National Ignition Facility - applications for inertial fusion energy and high-energy-density science",
"year_published": 1999,
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"Nuclear engineering",
"Physics",
"Nuclear physics",
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"abstract": "The Senior Committee on Environmental, Safety, and Economic Aspects of Magnetic Fusion Energy (ESECOM) summarizes its recent assessment of magnetic fusion energy's (MFE's) prospects for providing energy with economic, environmental, and safety characteristics that would be attractive compared with other energy sources (mainly fission) available in the time frame of the year 2015 and beyond. Accordingly, ESECOM has given particular attention to the interaction of environmental, safety, and economic characteristics of a variety of magnetic fusion reactors, and compared those fusion cases with a variety of fission cases. Eight fusion cases, two fusion-fission hybrid cases, and four fission cases are examined, using consistent economic and safety models, to permit exploration of the environmental, safety, and economic potential of fusion concepts using a wide range of possible materials choices, power densities, power conversion schemes, and fuel cycles.",
"URL": "https://www.ans.org/pubs/journals/fst/a_25084",
"title": "Exploring the Competitive Potential of Magnetic Fusion Energy: The Interaction of Economics with Safety and Environmental Characteristics",
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"Nuclear engineering",
"Fission",
"Variety (cybernetics)",
"Biochemical engineering",
"Range (aeronautics)",
"Electricity",
"Energy source",
"Computer science",
"Hybrid system",
"Radioactive waste"
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"abstract": "Indirect Drive Inertial Confinement Fusion Experiments on the National Ignition Facility (NIF) have achieved a burning plasma state with neutron yields exceeding 170 kJ, roughly 3 times the prior record and a necessary stage for igniting plasmas. The results are achieved despite multiple sources of degradations that lead to high variability in performance. Results shown here, for the first time, include an empirical correction factor for mode-2 asymmetry in the burning plasma regime in addition to previously determined corrections for radiative mix and mode-1. Analysis shows that including these three corrections alone accounts for the measured fusion performance variability in the two highest performing experimental campaigns on the NIF to within error. Here we quantify the performance sensitivity to mode-2 symmetry in the burning plasma regime and apply the results, in the form of an empirical correction to a 1D performance model. Furthermore, we find the sensitivity to mode-2 determined through a series of integrated 2D radiation hydrodynamic simulations to be consistent with the experimentally determined sensitivity only when including alpha-heating.",
"URL": "NaN",
"title": "The impact of low-mode symmetry on inertial fusion energy output in the burning plasma state.",
"year_published": 2024,
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"first_author": "J E Ralph",
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"abstract": "Measurements of plasma effects on materials are required in the design and evaluation of fusion reactor components. One of the more prevalent effects is ion impact desorption (IID) of surface impurities, which may influence plasma temperatures and fuel recycling rates. This paper describes the application of secondary ion mass spectrometry (SIMS) to measure IID processes. SIMS is well suited for laboratory measurements of plasma effects since the ion beam used for analysis also simulates the energetic particle flux emanating from a plasma. This attribute can be utilized to obtain IID cross sections. A low-energy ion accelerator, which produces mass-analyzed, neutral-free beams of H1+, H2+, and H3+ is used as a primary ion source. The release of impurities from a wall sample due to IID is monitored by observing the appropriate secondary ion emission rate. Cross sections for various ion, impurity, substrate combinations are determined as functions of incident ion energy and impact angle. This information is then used to calculate impurity release rates expected during reactor operation.",
"URL": "https://ui.adsabs.harvard.edu/abs/1983ITNS...30.1183B/abstract",
"title": "An Application of SIMS to Fusion Energy Research: Determination of Ion Impact Desorption Cross Sections",
"year_published": 1983,
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"Atomic physics",
"Ion source",
"Materials science",
"Fusion power",
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"abstract": "Large-current-capacity high-temperature superconducting (HTS) conductors using YBCO tapes are being considered as an option for the LHD-type fusion energy reactor FFHR. The typical operating current, magnetic field, and temperature of such conductors in FFHR are 100 kA, 13 T, and 20 K, respectively. A preliminary design of the HTS conductor has been proposed for the FFHR helical coils. Analyses have been performed on the proposed HTS conductor regarding thermal properties, mechanical structures, AC losses, and quench detection and protection. It is suggested that stainless steel might be a better choice for the outer jacket of the HTS conductor compared to aluminum alloy. Due to increased specific heats of conductor materials at 20 K, HTS magnets are supposed to be operated more stably compared to low-temperature superconducting (LTS) magnets operated at \u223c4 K. The required refrigeration power is also reduced. Therefore, using HTS conductors, it is considered to be viable to assemble the continuous helical coils in segments with joints of conductors, as additional heat generation at the joints can be taken care by utilizing the surplus refrigeration power. According to these analyses, HTS conductors seem to be promising for the FFHR coils.",
"URL": "http://ui.adsabs.harvard.edu/abs/2008PFR.....3S1049B/abstract",
"title": "High-Temperature Superconducting Coil Option for the LHD-Type Fusion Energy Reactor FFHR",
"year_published": 2008,
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"Electrical conductor",
"Fusion power",
"Heat generation",
"Electromagnetic coil",
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"Nuclear magnetic resonance",
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"first_author": "G. Bansal",
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"abstract": "Inertial fusion energy (IFE) research indicates that the energy generation by means of cryogenic fuel target compression requires that targets must be injected to the target chamber center at a rate of about 6 Hz. This requirement can be fulfilled only if the targets are free-standing. The most interesting results concerning the activity of the Lebedev Physical Institute in the area of free-standing targets (FST) fabrication, characterization and delivery are presented.",
"URL": "https://ui.adsabs.harvard.edu/abs/2005LPB....23..563K/abstract",
"title": "Free standing target technologies for inertial fusion energy: Target fabrication, characterization, and delivery",
"year_published": 2005,
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"Aerospace engineering",
"Nanotechnology",
"Inertial frame of reference",
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"first_author": "E. R. Koresheva",
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"abstract": "ION BEAM HEATED TARGET SIMULATIONS FOR WARM DENSE MATTER PHYSICS AND INERTIAL FUSION ENERGY J. J. Barnard 1 , J. Armijo 2 , D. S. Bailey 1 , A. Friedman 1 , F. M. Bieniosek 2 , E. Henestroza 2 , I. Kaganovich 3 , P. T. Leung 5 , B. G. Logan 2 , M.M. Marinak 1 , R. M. More 2 , S. F. Ng 2,5 , G. E. Penn 2 , L. J. Perkins 1 , S. Veitzer 4 , J. S. Wurtele 2 , S. S. Yu 2,5 , A. B. Zylstra 2 1. Lawrence Livermore National Laboratory, Livermore, CA 94550 USA 2. Lawrence Berkeley National Laboratory, Berkeley, CA 94720 USA 3. Princeton Plasma Physics Laboratory, Princeton, NJ 08543 USA 4. Tech-X Corporation, Boulder, CO 80303 USA 5. Chinese University Hong Kong, Hong Kong, China Abstract. Hydrodynamic simulations have been carried out using the multi-physics radiation hydrodynamics code HYDRA and the simplified one-dimensional hydrodynamics code DISH. We simulate possible targets for a near-term experiment at LBNL (the Neutralized Drift Compression Experiment, NDCX) and possible later experiments on a proposed facility (NDCX-II) for studies of warm dense matter and inertial fusion energy related beam-target coupling. Simulations of various target materials (including solids and foams) are presented. Experimental configurations include single pulse planar metallic solid and foam foils. Concepts for double-pulsed and ramped-energy pulses on cryogenic targets and foams have been simulated for exploring direct drive beam target coupling, and concepts and simulations for collapsing cylindrical and spherical bubbles to enhance temperature and pressure for warm dense matter studies *Work performed under the auspices of the U.S. Department of Energy under contract DE-AC52-07NA27344 at LLNL, and University of California contract DE-AC02- 05CH11231 at LBNL and contract DEFG0295ER40919 at PPPL. I. Introduction Heavy ion accelerators have long been advanced as drivers for inertial fusion energy (IFE), for their high efficiency, intrinsically high repetition rate, and their attractive final focus and chamber solutions. In a heavy ion fusion (HIF) driver, the final focus is accomplished using magnets (quadrupoles or solenoids) which can be shielded from the fusion microexplosions. The solid chamber wall can be shielded from the microexplosions using a flowing liquid salt, that acts as protection to the solid wall; an absorber of heat from the microexplosion; a heat transfer medium; and a breeder of the tritium component of the fuel. Because of high accelerator efficiency, both indirect drive targets and direct drive targets remain options for HIF. Indirect drive has relatively low intrinsic coupling efficiency (ratio of fuel kinetic energy to beam energy) because of the energy penalty in raising the temperature of the hohraum walls, but indirect drive targets",
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"title": "ION BEAM HEATED TARGET SIMULATIONS FOR WARM DENSE MATTER PHYSICS AND INERTIAL FUSION ENERGY",
"year_published": 2008,
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"abstract": "LBNL-41375 UC-419 H I F A N 936 Self-Pinched Beam Transport Experiments Relevant to Heavy Ion Driven Inertial Fusion Energy January 30, 1998 W. B . Herrmannsfeldt Stanford Linear Accelerator Center, Stanford, C A 94309 R. O. Bangerter, T. J. Fessenden, E . P. Lee, S. S. Y u Lawrence Berkeley National Laboratory. Berkeley, C A 94720 C. L . Olson Sandia National Laboratories, Albuquerque, N M 87185 D. R. Welch Mission Research Corporation, Albuquerque, N M 87106 J. J. Barnard, A . Friedman, B . G. Logan, R. W. Moir Lawrence Livermore National Laboratory, Livermore, C A 94551 I. Haber, P. F. Ottinger, F. C. Young Naval Research Laboratory, Washington, D C 20375 R. R. Peterson University of Wisconsin, Madison, WI 53706 R. J. Briggs Science Applications International Corporation, Pleasanton, C A 94588 This work was supported by the Director, Office of Energy Research [Office of Fusion Energy Science], U . S. Department of Energy under Contract No. DE-AC03-76SF00098.",
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"abstract": "This paper provides neutronics analyses of the Xcimer Energy Corporation (XEC) HYLIFE-III Inertial Fusion Energy Power Plant concept. This design is based on the thick-liquid-wall HYLIFE-II reactor, but with much larger fusion yield, due to enhanced driver energy. Although HYLIFE-II neutronics was extensively studied, the differences between the two concepts suggested new analyses are required. Further, computational advances in neutronics calculations also motivate updating results from more than 25 years ago. The neutron spectra emitted from the much larger yield hybrid Inertial Confinement Energy (IFE) target is presented. Selected breeding materials are compared by tritium breeding ratio (TBR), activation, and first wall protection where FLiBe is proposed as the overall best choice. The first wall neutron activation and structural damage, including gas generation in the wall, is presented for various FLiBe protective wet-wall thicknesses. Final optic neutron damage is also examined and results in optics long enough lifespan with moderate annealing temperatures. Some limited comparisons of first wall damage for ICF and Magnetic Confinement Fusion relevant conditions is presented. HYLIFE-III with FLiBe as the breeding material and first wall protection provides a very robust TBR above 1.2.",
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"sentence": "Further, computational advances in neutronics calculations also motivate updating results from more than 25 years ago.",
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"sentence": "The neutron spectra emitted from the much larger yield hybrid Inertial Confinement Energy IFE target is presented.",
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"sentence": "Selected breeding materials are compared by tritium breeding ratio TBR, activation, and first wall protection where FLiBe is proposed as the overall best choice.",
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"sentence": "The first wall neutron activation and structural damage, including gas generation in the wall, is presented for various FLiBe protective wet-wall thicknesses.",
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"sentence": "Final optic neutron damage is also examined and results in optics long enough lifespan with moderate annealing temperatures.",
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"abstract": "Irradiation creep is known to be an important process for structural materials in nuclear environments, potentially leading to creep failure at temperatures where thermal creep is generally negligible. While there is a great deal of data for irradiation creep in steels and zirconium alloys in light water reactor conditions, much less is known for first wall materials under fusion energy conditions. Lacking suitable fusion neutron sources for detailed experimentation, modeling, and simulation can help bridge the dose-rate and spectral-effects gap and produce quantifiable expectations for creep deformation of first wall materials under standard fusion conditions. In this paper, we develop a comprehensive model for irradiation creep created from merging a crystal plasticity representation of the dislocation microstructure and a defect evolution simulator that accounts for the entire cluster dimensionality space. Both approaches are linked by way of a climb velocity that captures dislocation-biased defect absorption and a dislocation strengthening term that reflects the accumulation of defect clusters in the system. We carry out our study in Fe under first wall fusion reactor conditions, characterized by a fusion neutron spectrum with average recoil energies of 20\u2009keV and a damage dose rate of \u22483\u00d710\u22127\u2009dpa/s at temperatures between 300 and 800\u2009K.",
"URL": "https://aip.scitation.org/doi/10.1063/5.0101561",
"title": "Physics-based model of irradiation creep for ferritic materials under fusion energy operation conditions",
"year_published": 2022,
"fields_of_study": [
"Creep",
"Materials science",
"Fusion power",
"Dislocation",
"Irradiation",
"Climb",
"Structural material",
"Fusion",
"Neutron",
"Neutron transport",
"Nuclear engineering",
"Nuclear physics",
"Composite material",
"Thermodynamics",
"Physics",
"Plasma",
"Linguistics",
"Philosophy",
"Engineering"
],
"first_author": "Qianran Yu",
"scholarly_citations_count": 1,
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"abstract": "There has been rapid progress in inertial fusion in the past few years. This progress spans the construction of ignition facilities, a wide range of target concepts and the pursuit of integrated programmes to develop fusion energy using lasers, ion beams and z-pinches.Two ignition facilities are under construction, the national ignition facility (NIF) in the United States and the laser megajoule (LMJ) in France, and both projects are progressing towards an initial experimental capability. The laser integration line prototype beamline for LMJ and the first four beams of NIF will be available for experiments in 2003. The full 192 beam capability of NIF will be available in 2009 and ignition experiments are expected to begin shortly after that time.There is steady progress in target science and target fabrication in preparation for indirect-drive ignition experiments on NIF. Advanced target designs may lead to 5\u201310 times more yield than initial target designs. There has also been excellent progress on the science of ion beam and z-pinch-driven indirect-drive targets.Excellent progress on direct-drive targets has been obtained on the Omega laser at the University of Rochester. This includes improved performance of targets with a pulse shape predicted to result in reduced hydrodynamic instability. Rochester has also obtained encouraging results from initial cryogenic implosions.There is widespread interest in the science of fast ignition because of its potential for achieving higher target gain with lower driver energy and relaxed target fabrication requirements. Researchers from Osaka have achieved outstanding implosion and heating results from the Gekko XII Petawatt facility and implosions suitable for fast ignition have been tested on the Omega laser.A broad-based programme to develop lasers and ion beams for inertial fusion energy (IFE) is under way with excellent progress in drivers, chambers, target fabrication and target injection. KrF and diode pumped solid-state lasers are being developed in conjunction with dry-wall chambers and direct-drive targets. Induction accelerators for heavy ions are being developed in conjunction with thick-liquid protected wall chambers and indirect-drive targets.",
"URL": "https://iopscience.iop.org/article/10.1088/0741-3335/45/12A/015",
"title": "The US inertial confinement fusion (ICF) ignition programme and the inertial fusion energy (IFE) programme",
"year_published": 2003,
"fields_of_study": [
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"Nuclear engineering",
"Physics",
"Beamline",
"Nova (laser)",
"Ignition system",
"Nanotechnology",
"Implosion",
"Fusion power",
"National Ignition Facility",
"Laser M\u00e9gajoule"
],
"first_author": "J. D. Lindl",
"scholarly_citations_count": 23,
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"sentence": "KrF and diode pumped solid-state lasers are being developed in conjunction with dry-wall chambers and direct-drive targets.",
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"sentence": "Induction accelerators for heavy ions are being developed in conjunction with thick-liquid protected wall chambers and indirect-drive targets.",
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{
"abstract": "This paper presents a summary of the papers presented at the 24th IAEA Fusion Energy Conference (San Diego, CA, October 2012) on magnetic confinement theory and modelling.",
"URL": "http://iopscience.iop.org/article/10.1088/0029-5515/53/10/104026",
"title": "Summary of the magnetic confinement theory and modelling activity presented at the 24th IAEA Fusion Energy Conference",
"year_published": 2013,
"fields_of_study": [
"Nuclear engineering",
"Physics",
"Magnetic confinement fusion",
"Fusion power",
"Engineering physics"
],
"first_author": "T.S. Hahm",
"scholarly_citations_count": 7,
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"abstract": "We have measured the cross section for the important fusion-energy reaction $^{2}\\mathrm{H}(\\mathrm{t},\\ensuremath{\\alpha})\\mathrm{n}$ at 17 energies over the triton bombarding energy range of 12.5-117 keV. This corresponds to an equivalent deuteron bombarding energy range of 8.3-78.1 keV and to a plasma temperature ($\\mathrm{kT}$) range of 0.7-18.8 keV. The cross section is accurate to 1.4% over most of the energy range, with the error rising to 4.8% at the lowest energy. These data are considerably more accurate than the previous d + t measurements in this energy range. We compare our data with those of other measurements and with an existing $R$-matrix analysis of the mass-5 system. We have also performed a single-level $R$-matrix analysis of a restricted data base that contains our data and have used that analysis to compute Maxwellian reactivities up to a plasma temperature of 20 keV. In addition, for calibration purposes, we measured to better than 1% absolute error the $^{2}\\mathrm{H}$(p,p)$^{2}\\mathrm{H}$ elastic differential cross section at six laboratory angles at a proton bombarding energy of 10.04 MeV.",
"URL": "http://inspirehep.net/record/212284",
"title": "Fusion-energy reaction H-2 (t, alpha) n from Et=12.5to117 keV",
"year_published": 1984,
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"Radiochemistry",
"Alpha (ethology)",
"Fusion power",
"Atomic physics",
"Energy (signal processing)",
"Nuclear reaction",
"Range (particle radiation)",
"Proton",
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"first_author": "Nelson Jarmie",
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"abstract": "Enhanced safety and performance improvements have been made to the liquid-wall HYLIFE reactor, yielding the current HYLIFE-II conceptual design. Liquid lithium has been replaced with a neutronically thick array of flowing molten-salt jets (Li[sub 2]BeF[sub 4] or Flibe), which will not burn, has a low tritium solubility and inventory, and protects the chamber walls, giving a robust design with a 30-yr lifetime. The tritium inventory is 0.5 g in the molten salt and 140 g in the metal of the tube walls, where it is less easily released. The 5-MJ driver is a recirculating induction accelerator estimated to cost $570 million (direct costs). Heavy-ion targets yield 350 MJ, six times per second, to produce 940 MW of electrical power for a cost of 6.5 cents/kW[center dot]h. Both larger and smaller yields are possible with correspondingly lower and higher pulse rates. When scaled up to 1934 MW (electric), the plant design has a calculated cost of electricity of 4.5 cents/kW[center dot]h. The design did not take into account potential improved plant availability and lower operations and maintenance costs compared with conventional power plant experience, resulting from the liquid wall protection. Such improvements would directly lower the electricity cost figures. For example,more\u00a0\u00bb if the availability can be raised from the conservatively assumed 75% to 85% and the annual cost of component replacement, operations, and maintenance can be reduced from 6% to 3% of direct cost, the cost of electricity would drop to 5.0 and 3.9 cents/kW[center dot]h for 1- and 2-GW (electric) cases. 50 refs., 15 figs., 3 tabs.\u00ab\u00a0less",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST94-A30234",
"title": "HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design \u2014 Final Report",
"year_published": 1994,
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"Nuclear physics",
"Materials science",
"Instrumentation",
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"abstract": "In heavy ion inertial fusion energy systems, intense beams of ions must be transported from the exit of the final focus magnet system through the target chamber to hit millimeter spot sizes on the target. In this paper, three different modes of beam propagation are examined: neutralized ballistic transport, assisted pinched transport, and self-pinched transport. The status of the authors' understanding of these three modes is summarized, and the constraints imposed by beam propagation upon the chamber environment, as well as their compatibility with various chamber and target concepts, are considered. It is concluded that on the basis of the present understanding, there is a reasonable range of parameter space where beams can propagate in thick-liquid-wall, wetted-wall, and dry-wall chambers.",
"URL": "https://www.tandfonline.com/doi/abs/10.13182/FST04-A584",
"title": "Impact of Beam Transport Method on Chamber and Driver Design for Heavy Ion Inertial Fusion Energy",
"year_published": 2004,
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"Physics",
"Ion",
"Magnet",
"Beam (structure)",
"Inertial frame of reference",
"Nuclear physics",
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"abstract": "Hydrodynamic simulations have been carried out using the multi-physics radiation hydrodynamics code HYDRA and the simplified one-dimensional hydrodynamics code DISH. We simulate possible targets for a near-term experiment at LBNL (the Neutralized Drift Compression Experiment, NDCX) and possible later experiments on a proposed facility (NDCX-II) for studies of warm dense matter and inertial fusion energy-related beam-target coupling. Simulations of various target materials (including solids and foams) are presented. Experimental configurations include single-pulse planar metallic solid and foam foils. Concepts for double-pulsed and ramped-energy pulses on cryogenic targets and foams have been simulated for exploring direct drive beam-target coupling, and concepts and simulations for collapsing cylindrical and spherical bubbles to enhance temperature and pressure for warm dense matter studies.",
"URL": "http://raman.physics.berkeley.edu/papers/IonBeamSimulations_NIMA_606_2009.pdf",
"title": "ION BEAM HEATED TARGET SIMULATIONS FOR WARM DENSE MATTER PHYSICS AND INERTIAL FUSION ENERGY",
"year_published": 2009,
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"Bonding in solids",
"Coupling",
"Physics",
"Planar",
"Inertial frame of reference",
"Cryogenics",
"Fusion power",
"Warm dense matter",
"Ion beam",
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"abstract": "The Burning Plasma Experiment (BPX), formerly known as the Compact Ignition Tokomak, will be a major advance in the design of a fusion reactor. The successful construction of fusion reactors will require extensive welding of thick-section stainless steel plates. Severe service conditions will be experienced by the structure. Operating temperatures will range from room temperature (300 K) to liquid nitrogen temperature (77 K), and perhaps even lower. The structure will be highly stressed, and subject to sudden impact loads if plasma disruptions occur. This demands a combination of high strength and high toughness from the weldments. Significant portions of the welding will be done in the field, so preweld and postweld heat treatments will be difficult. The thick sections to be welded will require a high deposition rate process, and will result in significant residual stresses in the materials. Inspection of these thick sections in complex geometries will be very difficult. All of these constraints make it essential that the welding procedures and alloys be well understood, and the mechanical properties of the welds and their heat-affected zones must be adequately characterized.",
"URL": "http://www.osti.gov/scitech/biblio/5806233",
"title": "Thick-Section Weldments in 21-6-9 and 316LN Stainless Steel for Fusion Energy Applications",
"year_published": 1992,
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"Metallurgy",
"Materials science",
"Welding",
"Fusion power",
"Inconel",
"Austenitic stainless steel",
"Residual stress",
"Fracture toughness",
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"first_author": "David Alexander",
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"abstract": "Melting from an array of three staggered, electrically heated cylinders imbedded in a paraffin (n-octadecane) has been studied. The shape of the melting front has been determined photographically, and the local heat transfer coefficients were measured using a shadowgraph technique. The experiments provide conclusive evidence of the important role played by natural convection on the timewise variation of the melt shape, the surface temperature and the instantaneous local as well as circumferentially averaged heat transfer coefficients around the imbedded heat sources. After a common solid-liquid interface is formed around the cylinders, natural convection circulation around each cylinder interacts strongly with the other two cylinders. The arrangement of heat sources affects significantly the melt shape but the circumferentially averaged instantaneous heat transfer coefficients differ only by about 10 percent for the two arrangements studied. The experimental findings indicate that natural convection effects are important and should be considered in analysis and design of systems involving phase change.",
"URL": "http://heattransfer.asmedigitalcollection.asme.org/article.aspx?articleid=1437038",
"title": "Latent Heat-of-Fusion Energy Storage: Experiments on Heat Transfer from Cylinders During Melting",
"year_published": 1979,
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"Thermal energy",
"Convection",
"Materials science",
"Heat transfer coefficient",
"Convective heat transfer",
"Heat transfer",
"Cylinder (engine)",
"Natural convection",
"Latent heat",
"Thermodynamics"
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"first_author": "A. G. Bathelt",
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"abstract": "In an inertial fusion energy (IFE) thick-liquid chamber design such as HYLIFE-II, a molten-salt is used to attenuate neutrons and protect the chamber structures from radiation damage. In the case of a fast ignition inertial fusion system, advanced targets have been proposed that may be self-sufficient in terms of tritium breeding (i.e. the amount of tritium bred in target exceeds the amount burned). This aspect allows for greater freedom when selecting a liquid for the protective blanket, given that lithium-bearing compounds are no longer required. Materials selection may now be based upon other characteristics, such as safety and environmental (S&E), pumping power, corrosion, and vapor pressure, along with others. The present work assesses the characteristics of many single, binary, and ternary molten-salts and liquid metals using the NIST Properties of Molten Salts Database. As an initial screening, liquids were evaluated for their S&E characteristics, which included an assessment of waste disposal rating (WDR), contact dose, and radioactive afterheat. Liquids that passed the S&E criteria were then evaluated for required pumping power. The pumping power was calculated using three components: velocity head losses, frictional losses, and lifting power. The results of the assessment are used to identify those materials that are suitable for potential liquid-chamber fast-ignition IFE concepts, from both the S&E and pumping power perspective. Recommendations for further analysis are also made.",
"URL": "https://www.osti.gov/servlets/purl/803169",
"title": "Liquid wall options for tritium-lean fast ignition inertial fusion energy power plants",
"year_published": 2002,
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"Nuclear engineering",
"Ignition system",
"Power (physics)",
"Nuclear physics",
"Vapor pressure",
"Fusion power",
"Blanket",
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"Environmental science",
"Nuclear reactor"
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"first_author": "Susana Reyes",
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"entity": "Molten-salts"
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"category": "Chemical Element or Compound",
"entity": "Liquid metals"
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"category": "Database",
"entity": "NIST Properties of Molten Salts Database"
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"sentence": "As an initial screening, liquids were evaluated for their SE characteristics, which included an assessment of waste disposal rating WDR, contact dose, and radioactive afterheat.",
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"sentence": "Liquids that passed the SE criteria were then evaluated for required pumping power.",
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"sentence": "The results of the assessment are used to identify those materials that are suitable for potential liquid-chamber fast-ignition IFE concepts, from both the SE and pumping power perspective.",
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"sentence": "Recommendations for further analysis are also made.",
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"abstract": "In this paper the feasibility and advantage of nuclear explosion deuterium-deuterium fusion to generate electricity are analyzed briefly.According to scale of 10 kt TNT nuclear explosion deuterium-deuterium fusion,the function of beat carrier on keeping energy and its amount,the action intensity of shock wave of nuclear explosion on chamber wall and bearing capacity of explosion camber wall are estimated.",
"URL": "https://en.cnki.com.cn/Article_en/CJFDTOTAL-HWDT200704016.htm",
"title": "Nuclear Explosion Deuterium-deuterium Fusion Power\u2014\u2014A Possible Way to Peaceful Use of Fusion Energy",
"year_published": 2007,
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"Nuclear engineering",
"Physics",
"Fusion",
"Nuclear physics",
"Fusion power",
"Nuclear explosion",
"Heat carrier",
"Deuterium",
"Deuterium burning",
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],
"first_author": "Liu Cheng-an",
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"abstract": "The Compact Torus Accelerator (CTA), under development at Lawrence Livermore National Laboratory, offers the promise of a low-cost, high-efficiency, high energy, high-power-density driver for ICF and MICF (Magnetically Insulated ICF) type fusion systems. A CTA with 100 MJ driver capacitor bank energy is predicted to deliver {approximately}30 MJ CT kinetic energy to a 1 cm{sup 2} target in several nanoseconds for a power density of {approximately}10{sup 16} watts/cm{sup 2}. The estimated cost of delivered energy is {approximately}3$/Joule, or $100M for 30 MJ. This driver appears to be cost-effective and, in this regard, is virtually alone among IFE drivers. We discuss indirect-drive ICF with a DT fusion energy gain Q = 70 for a total yield of 2 GJ. The CT can be guided to the target inside a several-meter-long disposable cone made of frozen Li{sub 2}BeF{sub 4}, the same material as the coolant. We have designed a power plant including CT injection, target emplacement, containment, energy recovery, and tritium breeding. The cost of electricity is predicted to be 4.8 {cents}/kWh, which is competitive with future coal and nuclear costs.",
"URL": "https://ans.tandfonline.com/doi/abs/10.13182/FST92-A29931",
"title": "Inertial Fusion Energy Power Plant Design Using the Compact Torus Accelerator: HYLIFE-CT",
"year_published": 1992,
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"Inertial confinement fusion",
"Nuclear engineering",
"Physics",
"Kinetic energy",
"Energy recovery",
"Type (model theory)",
"Energy (signal processing)",
"Fusion power",
"Cost effectiveness",
"Energy technology"
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"first_author": "Ralph W. Moir",
"scholarly_citations_count": 5,
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{
"abstract": "A new type of MeV ion generation at laser-plasma interaction has been measured based on the observation [1] that ps neodymium glass laser pulses of about TW and higher power do not produce the relativistic self-focusing based very high ion energies but more than 50 times lower energies. On top the strange observation was reported [fl that the number of the emitted fast ions did not change at variation of the laser focus intensity by a factor 30. This can be explained by the effect that without an inadiating prepulse, a pui plane gcmetnc skin layer interaction mechathsm occurs [2]. Neither relativistic self-focusing is possible nor the process of thermalization of quiver energy by quantum modified collisions. Following our conclusions about the difficulties for the fast ignitor concept of laser fi.ision [3], we can explain how these mechanisms can be used for studying the self-sustained fusion combustion waves [4] as known from the spark ignition at laser fusion. We further expect an improvement of the conditions for the experiments [5]with the highest laser fusion gains ever reported where even no pre-compression of the ftision plasma was necessary.",
"URL": "https://royalsoc.org.au/publications/journal_2000_on/J_Proc_RSNSW_Vol_145_Nos_443_444_Osman_(2002)_reprint.pdf",
"title": "New skin depth plasma interaction by ps-TW laser pulses and consequences for fusion energy",
"year_published": 2002,
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Ion",
"Thermalisation",
"Atomic physics",
"Fusion power",
"IGNITOR",
"Laser",
"Neodymium",
"Plasma"
],
"first_author": "Heinrich Hora",
"scholarly_citations_count": 5,
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"sentence": "Following our conclusions about the difficulties for the fast ignitor concept of laser fi.ision, we can explain how these mechanisms can be used for studying the self-sustained fusion combustion waves as known from the spark ignition at laser fusion.",
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"sentence": "We further expect an improvement of the conditions for the experiments with the highest laser fusion gains ever reported where even no pre-compression of the ftision plasma was necessary.",
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},
{
"abstract": "Hundred-joule, kilowatt-class lasers based on diode-pumped solid-state technologies, are being developed worldwide for laser-plasma interactions and as prototypes for fusion energy drivers. The goal of the Mercury Laser Project is to develop key technologies within an architectural framework that demonstrates basic building blocks for scaling to larger multi-kilojoule systems for inertial fusion energy (IFE) applications. Mercury has requirements that include: scalability to IFE beamlines, 10 Hz repetition rate, high efficiency, and 10 9 shot reliability. The Mercury laser has operated continuously for several hours at 55 J and 10 Hz with fourteen 4 x 6 cm 2 ytterbium doped strontium fluoroapatite amplifier slabs pumped by eight 100 kW diode arrays. A portion of the output 1047 nm was converted to 523 nm at 160 W average power with 73% conversion efficiency using yttrium calcium oxy-borate (YCOB).",
"URL": "https://inis.iaea.org/Search/search.aspx?orig_q=RN:39105609",
"title": "THE MERCURY PROJECT: A HIGH AVERAGE POWER, GAS-COOLED LASER FOR INERTIAL FUSION ENERGY DEVELOPMENT",
"year_published": 2007,
"fields_of_study": [
"Inertial confinement fusion",
"Optics",
"Materials science",
"Amplifier",
"Energy conversion efficiency",
"Fusion power",
"Mercury laser",
"Laser",
"Nuclear fusion",
"Thermonuclear fusion"
],
"first_author": "Andy J. Bayramian",
"scholarly_citations_count": 114,
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"sentence": "A portion of the output 1047 nm was converted to 523 nm at 160 W average power with 73 conversion efficiency using yttrium calcium oxy-borate YCOB.",
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{
"abstract": "A spherical torus (ST) fusion energy development path which is complementary to the proposed tokamak burning plasma experiments such as ITER is described. The ST strategy focuses on a compact component test facility (CTF) and high performance advanced regimes leading to more attractive Demo and power plant scale reactors. To provide the physical basis for the CTF an intermediate step needs to be taken, which we refer to as the 'next-step spherical torus' (NSST) device and which we examine in some detail herein. NSST is a 'performance extension' stage ST with a plasma current of 5?10?MA, R = 1.5?m, BT ? 2.6?T and the possibility of varying physical parameters. The mission of NSST is to (1) provide a sufficient physical basis for the design of a CTF; (2) explore advanced operating scenarios with high bootstrap current fraction and high performance which can be utilized by CTF, Demo, and power plants; and (3) contribute to the general science of high ? toroidal plasmas. The NSST is designed to utilize a TFTR-like site to minimize the cost and time required for design and construction.",
"URL": "http://iopscience.iop.org/article/10.1088/0029-5515/44/3/011/pdf",
"title": "Next-step spherical torus experiment and spherical torus strategy in the course of development of fusion energy",
"year_published": 2004,
"fields_of_study": [
"Tokamak",
"Nuclear engineering",
"Toroid",
"Magnetic confinement fusion",
"Power (physics)",
"Nuclear physics",
"Fusion power",
"Bootstrap current",
"Computer science",
"Power station",
"Torus"
],
"first_author": "M. Ono",
"scholarly_citations_count": 30,
"NER-RE": [
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"entity": "ITER"
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"sentence": "The ST strategy focuses on a compact component test facility CTF and high performance advanced regimes leading to more attractive Demo and power plant scale reactors.",
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{
"sentence": "To provide the physical basis for the CTF an intermediate step needs to be taken, which we refer to as the next-step spherical torus NSST device and which we examine in some detail herein.",
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},
{
"abstract": "Unconventional, promising approaches to inertial fusion energy (IFE) proposed and studied in the framework of IFE keep-in-touch activity at Frascati EURATOM-ENEA Association will be reconsidered for the present more advanced technological context associated to a planned large installations scenario. Then the possibility to generate laser-produced fast heavy-ion sources (e.g., Bi ions, tens GeV) will be explored taking as reference results obtained in the FIGEX experiment scaled toward thermonuclear regimes. A possible dimensioning of such sources will be also given as well as the associated laser requirements.",
"URL": "https://www.cambridge.org/core/journals/laser-and-particle-beams/article/studies-on-possible-alternative-schemes-based-on-twolaser-driver-for-inertial-fusion-energy-applications/C7BF124E6E20BA8BE785D7D9BB49F516",
"title": "Studies on possible alternative schemes based on two-laser driver for inertial fusion energy applications",
"year_published": 2009,
"fields_of_study": [
"Physics",
"Aerospace engineering",
"Inertial frame of reference",
"Nuclear physics",
"Fusion power",
"HiPER",
"Context (language use)",
"Laser",
"Thermonuclear fusion",
"Dimensioning"
],
"first_author": "C. Strangio",
"scholarly_citations_count": 4,
"NER-RE": [
{
"sentence": "Unconventional, promising approaches to inertial fusion energy IFE proposed and studied in the framework of IFE keep-in-touch activity at Frascati EURATOM-ENEA Association will be reconsidered for the present more advanced technological context associated to a planned large installations scenario.",
"entities": [
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{
"sentence": "Then the possibility to generate laser-produced fast heavy-ion sources .., Bi ions, tens GeV will be explored taking as reference results obtained in the FIGEX experiment scaled toward thermonuclear regimes.",
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{
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"entity": "Bi"
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"sentence": "A possible dimensioning of such sources will be also given as well as the associated laser requirements.",
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}
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},
{
"abstract": "A numerical and experimental investigation has been conducted to analyze the fluid dynamic aspects of the porous wetted wall protection scheme for inertial fusion energy (IFE) reactor first walls. ...",
"URL": "https://www.ans.org/pubs/journals/fst/a_280",
"title": "Fluid Dynamic Aspects of the Porous Wetted Wall Protection Scheme for Inertial Fusion Energy Reactors",
"year_published": 2003,
"fields_of_study": [
"Porous medium",
"Inertial confinement fusion",
"Inertial frame of reference",
"Materials science",
"Fusion power",
"Computer simulation",
"Mechanics",
"Porosity",
"Fluid dynamics"
],
"first_author": "Seungwon Shin",
"scholarly_citations_count": 7,
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"entity": "Porous wetted wall protection scheme"
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]
}
]
},
{
"abstract": "Electra is a high average power KrF laser system at the Naval Research Laboratory funded under the HAPL program. The goal of Electra is to develop the laser driver technologies needed, for an inertial fusion energy power plant. When run in an oscillator configuration the 500 kV, 100 kA e-beam pumped main amplifier produces 730 J with a 100 ns pulse width at 248 nm. KrF lasers have been shown to have intrinsic efficiencies of 12% leading to a projected wall plug efficiency of > 7% for an IFE system with demonstrated improvements in laser physics and pulse power technologies. As an oscillator the Electra main amplifier has run continuously at 1 Hz, 2.5 Hz, and 5 Hz for multi-thousand shot runs. This paper will discuss recent results from Electra including operation as a complete laser amplifier system, first demonstration of a new method to efficiently cool the hibachi foil with indications of a reduced penalty in laser uniformity, and design modifications to increase durability. Work sponsored by the US Department of Energy, NNSA/DP.",
"URL": "https://www.ans.org/pubs/journals/fst/a_8926",
"title": "Electra: An Electron Beam Pumped KrF Rep-Rate Laser System for Inertial Fusion Energy",
"year_published": 2009,
"fields_of_study": [
"Optics",
"Physics",
"Amplifier",
"Fusion power",
"Wall-plug efficiency",
"Laser science",
"Power station",
"Laser",
"Pulse-width modulation",
"Pulsed power"
],
"first_author": "Patrick M. Burns",
"scholarly_citations_count": 7,
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"abstract": "The survivability of the final optic, which must sit in the line of sight of high-energy neutrons and gamma rays, is a key issue for any laser-driven inertial fusion energy (IFE) concept. Previous ...",
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"abstract": "The Neutralized Drift Compression Experiment II (NDCX II) is an induction accelerator planned for initial commissioning in 2012. The final design calls for a {approx}3 MeV, {approx}30 A Li{sup +} ion beam, delivered in a bunch with characteristic pulse duration of 1 ns, and transverse dimension of order 1 mm. The purpose of NDCX II is to carry out experimental studies of material in the warm dense matter regime, and ion beam/hydrodynamic coupling experiments relevant to heavy ion based inertial fusion energy. In preparation for this new machine, we have carried out hydrodynamic simulations of ion-beam-heated, metallic solid targets, connecting quantities related to observables, such as brightness temperature and expansion velocity at the critical frequency, with the simulated fluid density, temperature, and velocity. We examine how these quantities depend on two commonly used equations of state.",
"URL": "http://www.osti.gov/scitech/biblio/981469-simulations-experimental-study-warm-dense-matter-inertial-fusion-energy-applications-ndcx-ii",
"title": "Simulations for experimental study of warm dense matter and inertial fusion energy applications on NDCX-II",
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"abstract": "Validity of decay heat calculations for safety designs of fusion reactors was investigated by using decay heat experimental data on thirty-two fusion reactor relevant materials obtained at the 14-MeV neutron source facility of FNS in JAERI. Calculation codes developed in Japan, ACT4 and CINAC version 4, and nuclear data bases such as JENDL/Act-96, FENDL/A-2.0 and Lib90 were used for the calculation. Although several corrections in algorithms for both the calculation codes were needed, it was shown by comparing calculated results with the experimental data that most of activation cross sections and decay data were adequate. In cases of type 316 stainless steel and copper which were important for ITER, prediction accuracy of decay heat within \u00b110% was confirmed. However, it was pointed out that there were some problems in parts of data such as improper activation cross sections, e.g., the 92Mo(n, 2n)91gMo reaction in FENDL, and lack of activation cross section data, e.g., the 138Ba(n, 2n)137mBa reaction in JENDL. Modifications of cross section data were recommended for 19 reactions in JENDL and FENDL. It was also pointed out that X-ray and conversion electron energies should be included in decay data.",
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"title": "Experimental Validation of Decay Heat Calculation Codes and Associated Nuclear Data Libraries for Fusion Energy.",
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"abstract": "A series of cryogenic, layered deuterium-tritium (DT) implosions have produced, for the first time, fusion energy output twice the peak kinetic energy of the imploding shell. These experiments at the National Ignition Facility utilized high density carbon ablators with a three-shock laser pulse (1.5 MJ in 7.5\u00a0ns) to irradiate low gas-filled (0.3\u2009\u2009mg/cc of helium) bare depleted uranium hohlraums, resulting in a peak hohlraum radiative temperature \u223c290\u2009\u2009eV. The imploding shell, composed of the nonablated high density carbon and the DT cryogenic layer, is, thus, driven to velocity on the order of 380\u2009\u2009km/s resulting in a peak kinetic energy of \u223c21\u2009\u2009kJ, which once stagnated produced a total DT neutron yield of 1.9\u00d710^{16} (shot N170827) corresponding to an output fusion energy of 54\u00a0kJ. Time dependent low mode asymmetries that limited further progress of implosions have now been controlled, leading to an increased compression of the hot spot. It resulted in hot spot areal density (\u03c1r\u223c0.3\u2009\u2009g/cm^{2}) and stagnation pressure (\u223c360\u2009\u2009Gbar) never before achieved in a laboratory experiment.",
"URL": "https://ui.adsabs.harvard.edu/abs/2018PhRvL.120x5003L/abstract",
"title": "Fusion Energy Output Greater than the Kinetic Energy of an Imploding Shell at the National Ignition Facility.",
"year_published": 2018,
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"National Ignition Facility",
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"abstract": "Proliferation concerns have generally been associated with the acquisition of the fissile material needed for nuclear weapons; however, the spread of the knowledge needed to build very light and po...",
"URL": "https://journals.sagepub.com/doi/abs/10.1177/0096340211407562",
"title": "Inertial confinement fusion energy R&D and nuclear proliferation: The need for direct and transparent review",
"year_published": 2011,
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"Nuclear engineering",
"Physics",
"Energy (signal processing)",
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"abstract": "A fast-opening, high-throughput gas valve and its application to inertial fusion energy (IFE) research and development are described. The valve is a pilot type with two stages of active components. The pilot or first stage section is magnetically driven and equipped with a 4.2-mm-diam orifice. The pilot valve is energized to initiate operations and dumps gas from the upstream section of the second stage to the main valve outlet, and the resultant pressure differential across the large (22.3-mm-diam) output orifice seat causes mechanical activation of the second stage. Both stages are equipped with hard polyimide stem tips and springs for sealing. The valve has been operated reliably with helium gas at pressures in the range of 4\u201335 bar and frequencies up to 6 Hz, with maximum flow rates of \u2248106\u200aTorr\u200al/s. The valve was developed to provide helium propellant gas for accelerating IFE targets to speeds up to 400 m/s in an experimental injector system under construction by General Atomics.",
"URL": "http://ui.adsabs.harvard.edu/abs/2004RScI...75..270C/abstract",
"title": "Fast-opening, high-throughput gas valve and application for inertial fusion energy R&D",
"year_published": 2004,
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"Injector",
"Pilot valve",
"Maximum flow problem",
"Bar (unit)",
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"Fusion power",
"Helium",
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"first_author": "S. K. Combs",
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"abstract": "During the past 2 yr, significant progress has been made in several areas related to the safety and environmental (S and E) aspects of inertial fusion energy (IFE). An updated methodology has been developed, and accident analyses have been performed for two IFE conceptual power plants and a target fabrication facility. Parallel to the consequence analyses of different accident scenarios, ongoing studies of accident initiating events are being used to support safety assessment and create a basic framework of types of events to consider in future risk characterization of new plant designs. Target designers/fabrication specialists have been provided with ranking information related to the S and E characteristics of candidate target materials. We have revisited waste management options for IFE, introducing the concept of clearance versus the traditional shallow land burial. A brief summary of results in each of these activities is given, and plans for future work are outlined.",
"URL": "https://www.osti.gov/scitech/biblio/20845916-safety-environmental-aspects-inertial-fusion-energy-overview-recent-activities-developments-united-states",
"title": "Safety and environmental aspects of inertial fusion energy: An overview of recent activities and developments in the United States",
"year_published": 2003,
"fields_of_study": [
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"Risk assessment",
"Inertial frame of reference",
"Work (electrical)",
"Ranking",
"Shallow land burial",
"Future risk",
"Computer science"
],
"first_author": "Susana Reyes",
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{
"sentence": "An updated methodology has been developed, and accident analyses have been performed for two IFE conceptual power plants and a target fabrication facility.",
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"sentence": "Target designersfabrication specialists have been provided with ranking information related to the S and E characteristics of candidate target materials.",
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"abstract": "A very smooth, highly-reflective coating on IFE (Inertial Fusion Energy) targets is essential for direct-drive ignition. An Au/Pd (gold-palladium alloy) is sputter coated onto the surface of an IFE target to improve the energy release from the target compression and thermonuclear reaction. It is also necessary to reflect the black body infrared radiation experienced while traveling into the chamber and preserve the delicate frozen deuterium and tritium ice inside. The coating must remain intact, without any ?pinhole? defects, which requires it be very durable and any handling techniques, such as transfer from the layering system to the injector, be gentle. The coatings were initially tested by physically impacting two targets together to simulate motion in a fluidized bed where most of the damage is estimated to occur. The coatings were also tested in tension to better understand the adhesion of the coating. Variations in the coating parameters were explored and optimized to produce a low-stress, smooth coating of Au/Pd, which was found to have better resistance to damage than the current coatings. Additionally, several novel methods for improving the coating's resistance to damage were investigated. One example is coating a sub-layer between the plastic shell and the Au/Pd coating using titanium as the bond enhancer. The initial results of the multi- layered coating performed more than twice as well as the best standard Au/Pd coating previously tested. This shows promise for the use of an interlayer to promote better bonding of the outer metallic reflective coating to the plastic shell.",
"URL": "https://ieeexplore.ieee.org/document/5415625/",
"title": "A method for characterizing and improving the damage resistance of the outer metallic coatings on Inertial Fusion Energy targets",
"year_published": 2010,
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"Inertial confinement fusion",
"Composite material",
"Materials science",
"Sputtering",
"Fusion power",
"Coating",
"Sputter deposition",
"Sheet resistance",
"Nuclear fusion",
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"abstract": "The recently obtained closed-form representation of the non-resonant thermonuclear reaction rate by a generalized hypergeometric function (Meijer's G-function) is used for a fusion yield calculation. A simplified physical model for the hydrodynamical processes in a fusion plasma compressed and heated by a laser-driven spherical shock wave permits calculation of the released fusion energy by integrating the thermonuclear reaction rate over the temperature. With the aid of the closed-form representation of the reaction rate this fusion energy production integral is approximation-free evaluated. After computing numerical factors, the approximate representation of the fusion energy yield given until now in the literature is compared with the more accurate ones obtained in this paper, and the apparent discrepancies are discussed.",
"URL": "http://ui.adsabs.harvard.edu/abs/1981PlPh...23..399H/abstract",
"title": "Analytical representation of the thermonuclear reaction rate and fusion energy production in a spherical plasma shock wave",
"year_published": 1981,
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"Physics",
"Generalized hypergeometric function",
"Fusion",
"Reaction rate",
"Fusion power",
"Yield (chemistry)",
"Mechanics",
"Shock wave",
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"Plasma"
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"abstract": "The methods of industrial ecology have been applied to the selection of a high-Z material for indirect-drive targets in the HYLIFE-II reactor. We quantify physical, chemical, and radiological impac...",
"URL": "https://ans.org/pubs/journals/fst/a_42297",
"title": "Industrial Ecology for Inertial Fusion Energy: Selection of High-Z Material for HYLIFE-II Targets",
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"abstract": "In heavy ion inertial fusion energy systems, intense beams of ions must be transported from the exit of the final focus magnet system through the target chamber to hit millimeter spot sizes on the target. In this paper, we examine three different modes of beam propagation: neutralized ballistic transport, assisted pinched transport, and self-pinched transport. The status of our understanding of these three modes is summarized, and the constraints imposed by beam propagation upon the chamber environment, as well as their compatibility with various chamber and target concepts, are considered. We conclude that, on the basis of our present understanding, there is a reasonable range of parameter space where beams can propagate in thick-liquid wall, wetted-wall, and dry-wall chambers.",
"URL": "http://www-ferp.ucsd.edu/LIB/REPORT/JOURNAL/FST/04-FST-Rose.pdf",
"title": "Impact of beam transport method on chamber and driver design for heavy ion inertial fusion energy",
"year_published": 2002,
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"abstract": "This paper provides a summary overview, based on papers presented at the 25th IAEA Fusion Energy Conference (FEC), in the area of magnetic confinement experiments related to stability (EX/S), wave\u2013plasma interactions, current drive, heating, energetic particles (EX/W) and innovative confinement concepts (ICCs). A selection of results that represent progress made since the last FEC in a few important thematic areas that are relevant for the successful and safe operation of future fusion devices like ITER, is highlighted.",
"URL": "http://iopscience.iop.org/article/10.1088/0029-5515/55/10/104024/pdf",
"title": "25th IAEA Fusion Energy Conference: summary of sessions EX/S, EX/W and ICC",
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"abstract": "Remote systems will be required in the High Yield Lithium Injection Fusion Energy Converter power plant proposed by Lawrence Livermore Laboratory. During inspection operations, viewing of the chamber interior and certain pumps, valve fittings and welds must be done remotely. Ideas for remote maintenance of laser beam blast baffles, optics, and target material traps are described. Radioisotope sources and their distributions, and exposure rates at various points in the reactor vicinity are presented.",
"URL": "https://digital.library.unt.edu/ark:/67531/metadc1210636/",
"title": "Remote systems requirements of the High Yield Lithium Injection Fusion Energy (HYLIFE) converter concept",
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"abstract": "This paper presents a summary of the papers presented at the 23rd IAEA Fusion Energy Conference (Daejeon, October 2010) on magnetic confinement theory and modelling.",
"URL": "https://ui.adsabs.harvard.edu/abs/2011NucFu..51i4003G/abstract",
"title": "Summary of the magnetic confinement theory and modelling activity presented at the 23rd IAEA Fusion Energy Conference",
"year_published": 2011,
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"abstract": "Validity of decay heat calculations for safety designs of fusion reactors was investigated by using decay heat experimental data on thirty-two fusion reactor relevant materials obtained at the 14-MeV neutron source facility of FNS in JAERI. Calculation codes developed in Japan, ACT4 and CINAC version 4, and nuclear data bases such as JENDL/Act-96, FENDL/A-2.0 and Lib90 were used for the calculation. Although several corrections in algorithms for both the calculation codes were needed, it was shown by comparing calculated results with the experimental data that most of activation cross sections and decay data were adequate. In cases of type 316 stainless steel and copper which were important for ITER, prediction accuracy of decay heat within \u00b110% was confirmed. However, it was pointed out that there were some problems in parts of data such as improper activation cross sections, e.g., the 92Mo(n, 2n)91gMo reaction in FENDL, and lack of activation cross section data, e.g., the 138Ba(n, 2n)137mBa reaction in ...",
"URL": "https://www.tandfonline.com/doi/abs/10.1080/18811248.2001.9715007",
"title": "Experimental Validation of Decay Heat Calculation codes and Associated Nuclear Data Libraries for Fusion Energy",
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"Nuclear physics",
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"abstract": "A scheme to suppress the ablative Rayleigh-Taylor (RT) instability using high-Z doped plastic target (brominated polystyrene;CHBr) has been proposed for a directly laser-driven IFE target. When an intense laser irradiates directly onto a high-Z doped target, radiation emitted from a corona plasma propagates and deposits locally its energy inside the target. The enhanced radiation forms the double-ablation structure, which consists of primaryelectron conduction ablation front and secondary radiative ablation front. The radiative ablation in the double-ablation structure has many advantages to suppress the growth of the RT instability in analogy of the indirect-drive approach, i.e. large mass ablation rate, long density scale length and low peak density. Two-dimensional (2D) hydrodynamic simulation code shows strong suppression of the RT instability in a brominated plastic (CHBr) target compared with that in an undoped polystyrene (CH) target. RT growth rates evaluated theoretically using the Betti-Goncharov procedure with one-dimensional(1D) radiation-hydrodynamic simulation are in good agreement with 2D simulation results. Several experiments were performed at the GEKKO XII- HIPER (High Intensity Plasma Experimental Research) laser facility. A trajectory of a laser-driven CHBr target observed in experiment was reproduced fairly well by 1D simulation code. The double-ablation structure formed inside a directly laser-driven CHBr target was clearly observed in experiments for the first time The strong suppression of the RT instability in the CHBr target was confirmed in experiments with face-on and side-on x-ray backlighting technique.",
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"abstract": "Rayleigh-Taylor instability of a laser accelerated ablative surface of a thin target shell with an incompressible fluid saturated porous lining is investigated using linear stability analysis. A simple theory based on replacing the no-slip effect with the Saffman slip condition is proposed. It is shown that the growth rate is greatly reduced over the value it would have if the shell is bounded by an impermeable boundary. This is useful in the very effective extraction of inertial fusion energy.",
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"abstract": "Solid-liquid phase-change heat transfer has been studied experimentally in several test modules simulating latent heat-of-fusion thermal energy storage systems. Basic data about motion of and convective heat transfer (resulting from natural convection in the melt) at the solid-liquid interface have been obtained, using paraffins and salt hydrates as phase change materials. Experimental heat transfer results are summarized in the paper, and predictions for the solid-liquid interface motions are compared with the data obtained.",
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"abstract": "The sessions of experiments EX/D, EX/S and EX/W covering (D) Plasma\u2013material interactions, Divertors, Limiters, SOL, (S) Stability, (W) Wave\u2013plasma interactions, Current drive, Heating and Energetic particles are summarized in this paper. These general topics are divided into two categories, which are (1) ITER oriented and (2) ITER/DEMO oriented corresponding to the subject of each topic and considering the road map of fusion research. Topics in the ITER oriented category are strongly linked to the present direction of the fusion research for ITER, namely tokamak research, whereas issues in the ITER/DEMO oriented category are generally common issues for both tokamaks and helical devices.",
"URL": "https://iopscience.iop.org/article/10.1088/0029-5515/49/10/104001/pdf",
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"abstract": "By changing the temperature of a LiTaO3 pyroelectric double\u2010crystal arrangement in a deuterium gas environment, deuterium ions were produced and accelerated towards a tritiated target, producing 14 MeV neutrons via the 3H(d,n)4He nuclear fusion reaction.",
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"abstract": "Commercial inertial fusion energy power plants will require 5-20Hz fusion target injection rates for utility-scale power production. To mitigate damage from target emission, some designs include a ...",
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"abstract": "An overview is given of recent experimental results in the areas of divertor and exhaust, stability and waves and fast particles presented at the 2006 IAEA Fusion Energy Conference. Important new findings are presented from fusion devices worldwide, with a strong focus towards the needs of the major next step fusion experiment ITER.",
"URL": "http://pubman.mpdl.mpg.de/pubman/item/escidoc:2143231",
"title": "21st IAEA Fusion Energy Conference: Summary of Sessions EX/D, EX/S and EX/W",
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"abstract": "Previously published calculations predict that the \u201cstaged z-pinch\u201d (SZP) can achieve 400\u2009MJ of fusion yield on a Z-class machine. The SZP is touted to need no external preheat mechanism and no external pre-magnetization method. Instead, it is claimed that the imploding liner can adequately \u201cshock preheat\u201d the fuel and magnetic field diffusion through the liner can adequately magnetize the fuel. In this paper, we analyze a number of published SZP calculations and demonstrate that the calculations have major errors\u2014the computer code used to do the calculations does not appear to be accurately solving the physical model it is intended to solve. A variety of independent analyses lead to this conclusion. This conclusion is confirmed by detailed one-dimensional magnetohydrodynamic (MHD) calculations conducted on different computer codes using a variety of proposed SZP operating parameters. Although using parameters similar or identical to the published calculations, our MHD calculations do not reach fusion conditions; there is no conceivable modification of the parameters that would lead to high-gain fusion conditions using these other codes. Our analyses and a review of the magnetized target parameter space leads to further conclusion that the SZP should not be considered to be a potential high-gain fusion source.",
"URL": "http://ui.adsabs.harvard.edu/abs/2018PhPl...25j2707L/abstract",
"title": "The staged z-pinch as a potential high gain fusion energy source: An independent review, a negative conclusion",
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"abstract": "The accuracy of a position measurement method using the Arago spot is reported for an inertial fusion energy (IFE) target tracking system, where the position of the target is determined by the position of the Arago spot, which is a bright spot appearing in the central portion of the diffraction pattern of a spherical obstacle. We use a He\u2013Ne laser as the light source and a charge-coupled device (CCD) camera with a microscope objective lens to magnify and record the diffraction pattern of a spherical target. We examine two different algorithms to determine the center of the Arago spot in order to compare the measurement performances. The experimental results show that the position of a 5-mm-diameter target can be obtained with a measurement resolution of 1 \u00b5m and an rms measurement error of less than 0.2 \u00b5m for both algorithms when the distance between the target and the microscope objective lens is 5 cm.",
"URL": "http://ci.nii.ac.jp/naid/150000049365",
"title": "Accuracy of position measurement method using arago spot for inertial fusion energy target tracking system",
"year_published": 2007,
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"abstract": "This article presents the concept of unlimited fusion-energy station (U-FESTA), comprising a fusion power plant and a lithium (Li) recovery facility to recover Li from seawater, for example the Li-separation method by ionic conductor (LiSMIC). To realize the U-FESTA, we discuss the relationship among the seawater-based Li-recovery efficiency, blanket technology on 6Li enrichment, intake cooling seawater in a power plant, and the blanket-replacement period.",
"URL": "https://www.jstage.jst.go.jp/article/pfr/18/0/18_1205077/_pdf",
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"abstract": "Feasibility studies on applying high-temperature superconductors (HTS) to the heliotron-type fusion energy reactor FFHR are being carried out. Using HTS, we consider that the three-dimensional helical coils with a ~40 m diameter can be constructed without preparing a huge winding machine. A practical method for realizing this concept is proposed. The electromagnetic stress inside the helical coil packs is examined using an FEM analysis for double-pancake windings. The effect of error magnetic field generated by the shielding currents in HTS tapes is also examined.",
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"title": "Design Progress on the High-Temperature Superconducting Coil Option for the Heliotron-Type Fusion Energy Reactor FFHR",
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"abstract": "PROGRESS IN HEAVY ION DRIVEN INERTIAL FUSION ENERGY: FROM SCALED EXPERIMENTS TO THE INTEGRATED RESEARCH EXPERIMENT * J. J. Barnard 1 , L. E. Ahle 1 , D. Baca 2 , R. O. Bangerter 2 , F. M. Bieniosek 2 , C. M. Celata 2 , E. Chacon-Golcher 2 , R. C. Davidson 3 , A. Faltens 2 , A. Friedman 1 , R.M. Franks 2 , D. P. Grote 1 , I. Haber 4 , E. Henestroza 2 , M. J. L. de Hoon 2 , I. Kaganovich 3 , V. P. Karpenko 1 , R. A. Kishek 5 , J. W. Kwan 2 , E. P. Lee 2 , B. G. Logan 1 , S.M. Lund 1 , W. R. Meier 1 , A. W. Molvik 1 , C. Olson 7 , L.R. Prost 2 , H. Qin 3 , D. Rose 6 , G-L. Sabbi 2 , T. C. Sangster 1 , P. A. Seidl 2 , W. M. Sharp 1 , D. Shuman 2 , J.L. Vay 2 , W.L. Waldron 2 , D. Welch 6 , S.S. Yu 2 1. Lawrence Livermore National Laboratory, Livermore, CA; 2. Lawrence Berkeley National Laboratory, Berkeley, CA; 3. Princeton Plasma Physics Laboratory, Princeton, NJ; 4. Naval Research Laboratory, Washington, D.C.; 5. University of Maryland, College Park, MD 6.Mission Research Corporation, Albuquerque, NM 7.Sandia National Laboratory, Albuquerque, NM Abstract The promise of inertial fusion energy driven by heavy ion beams requires the development of accelerators that produce ion currents (~100's Amperes/beam) and ion energies (~1 - 10 GeV) that have not been achieved simultaneously in any existing accelerator. The high currents imply high generalized perveances, large tune depressions, and high space charge potentials of the beam center relative to the beam pipe. Many of the scientific issues associated with ion beams of high perveance and large tune depression have been addressed over the last two decades on scaled experiments at Lawrence Berkeley and Lawrence Livermore National Laboratories, the University of Maryland, and elsewhere. The additional requirement of high space charge potential (or equivalently high line charge density) gives rise to effects (particularly the role of electrons in beam transport) which must be understood before proceeding to a large scale accelerator. The first phase of a new series of experiments in Heavy Ion Fusion Virtual National Laboratory (HIF VNL), the High Current Experiments (HCX), is now being constructed at LBNL. The mission of the HCX will be to transport beams with driver line charge density so as to investigate the physics of this regime, including constraints on the maximum radial filling factor of the beam through the pipe. This factor is important for determining both cost and reliability of a driver scale accelerator. The HCX will provide data for design of the next steps in the sequence of experiments leading to an inertial fusion energy power plant. The focus of the program after the HCX will be on integration of all of the manipulations required for a driver. In the near term following HCX, an Integrated Beam Experiment (IBX) of the same general scale as the HCX is envisioned. Figure 1. Schematic of the stages and beam manipulations required in a Heavy Ion Fusion driver. This work was performed under the auspices of the U.S. Department of Energy under University of California contract W-7405-ENG-48 at LLNL, and University of California contract DE-AC03-76SF00098 at LBNL, and PPPL contract",
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"abstract": "AbstractFeasibility studies on applying high-temperature superconductors (HTS) to the heliotron-type fusion energy reactor FFHR are being carried out. Using HTS, we consider that the three-dimensional helical coils with a ~40 m diameter can be constructed without preparing a huge winding machine. A practical method for realizing this concept is proposed. The electromagnetic stress inside the helical coil packs is examined using an FEM analysis for double-pancake windings. The effect of error magnetic field generated by the shielding currents in HTS tapes is also examined.",
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"abstract": "The group of 27 papers published in this special issue of Nuclear Fusion aims to monitor the worldwide progress made in the period 2008\u20132010 in the field of thermonuclear fusion. Of these papers, 22 are based on overview reports presented at the 23rd Fusion Energy Conference (FEC 2010) and five are summary reports. The conference was hosted by the Republic of Korea and organized by the IAEA in cooperation with the National Fusion Research Institute and the Daejeon Metropolitan City. It took place in Daejeon on 11\u201316 October 2010. The overviews presented at the conference have been rewritten and extended for the purpose of this special issue and submitted to the standard double-referee peer-review of Nuclear Fusion. The articles are placed in the following sequence: Conference summaries of the sessions devoted to: Tokamak and stellarator experiments, experimental divertor physics and plasma wall interaction experiments, stability experiments and waves and fast particles; ITER activities, fusion technology, safety and economics; Magnetic confinement theory and modelling; Inertial confinement fusion; Innovative confinement concepts, operational scenarios and confinement. Overview articles, presented in programme order, are as follows: Tokamaks Overview of KSTAR initial experiments; Recent progress in RF heating and long-pulse experiments on EAST; Overview of JET results; DIII-D contributions toward the scientific basis for sustained burning plasmas; Overview of JT-60U results toward the resolution of key physics and engineering issues in ITER and JT-60SA; Overview of physics results from NSTX; Overview of ASDEX Upgrade results; Overview of physics results from MAST; Contribution of Tore Supra in preparation of ITER; Overview of FTU results; Overview of experimental results on the HL-2A tokamak; Progress and scientific results in the TCV tokamak; Overview of the JT-60SA project; Recent results of the T-10 tokamak; The reconstruction and research progress of the TEXT-U tokamak in China. Other MCF Overview of results from the Large Helical Device; Overview of TJ-II experiments; Overview of the RFX fusion science program. ICF Progress toward ignition on the National Ignition Facility; Studying ignition schemes on European laser facilities; Cross device or cross programme topical overviews Effects of 3D magnetic perturbations on toroidal plasmas; Toroidal momentum transport. We trust that, as usual, this issue will be a useful resource for the community and we thank all of the authors and referees for their hard work in preparing the papers for publication. Whilst the number of overview reports is the same as for the Geneva FEC special issue (2009 Nucl. Fusion 49 100201), we are pleased to note that we have a complete set of summaries in this issue.",
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"entity": "FTU"
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"category": "Nuclear Fusion Experimental Facility",
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"sentence": "The reconstruction and research progress of the TEXT-U tokamak in China.",
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"category": "Nuclear Fusion Experimental Facility",
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"category": "Nuclear Fusion Device Type",
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"entity": "China"
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]
},
{
"sentence": "Other MCF Overview of results from the Large Helical Device Overview of TJ-II experiments Overview of the RFX fusion science program.",
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"category": "Nuclear Fusion Experimental Facility",
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},
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"sentence": "ICF Progress toward ignition on the National Ignition Facility Studying ignition schemes on European laser facilities Cross device or cross programme topical overviews Effects of 3D magnetic perturbations on toroidal plasmas Toroidal momentum transport.",
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"sentence": "We trust that, as usual, this issue will be a useful resource for the community and we thank all of the authors and referees for their hard work in preparing the papers for publication.",
"entities": []
},
{
"sentence": "Whilst the number of overview reports is the same as for the Geneva FEC special issue 2009 Nucl.",
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"entity": "2009"
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"sentence": "Fusion 49 100201, we are pleased to note that we have a complete set of summaries in this issue.",
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"abstract": "200 kW laser diode pumping module aimed for IFE driver was developed. The pumping optics for the uniform irradiation was applied to this module. As a result, 80% filling factor for the pumping distribution was achieved. The maximum peak power of 226 kW was obtained at the 150 \u03bcs pump duration. The E-O conversion efficiency over 50% was achieved.",
"URL": "https://joi.jlc.jst.go.jp/JST.JSTAGE/ieejeiss/128.707?from=CrossRef",
"title": "Large-Scale 200-kW Laser Diode Pumping Module for Inertial Fusion Energy Driver HALNA",
"year_published": 2008,
"fields_of_study": [
"Inertial confinement fusion",
"Optics",
"Engineering",
"Diode-pumped solid-state laser",
"Power (physics)",
"Energy conversion efficiency",
"Fusion power",
"Laser diode",
"Scale (ratio)",
"Filling factor"
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"first_author": "Takashi Kurita",
"scholarly_citations_count": 2,
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"abstract": "Analysis is presented that shows that the recent paper by Ruskov et al. [Phys. Plasmas 27, 042709, (2020)] has a number of errors. In particular, it is shown that the Mach2 code, as used in the paper, behaves in a number of nonphysical ways.",
"URL": "https://ui.adsabs.harvard.edu/abs/2021PhPl...28a4701L/abstract",
"title": "Comment on \"The staged z-pinch as a potential fusion energy source\" [Phys. Plasmas 27, 042709 (2020)]",
"year_published": 2021,
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"Nuclear physics",
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"first_author": "Irvin R. Lindemuth",
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"abstract": "The development of a high-repetition-rate (rep-rate) electron-beam (e-beam)-pumped KrF laser is described. In this study, we aim to achieve pulsed laser outputs of 20 J/80 ns at a rep rate of 1 Hz. The key issues are heat management in the diode foils and introduction of long-lifetime switches into the pulsed-power system. E-beam generation experiments have been started with initial test results of twenty consecutive shots at 1 Hz. Improvement in the energy-transfer efficiency in the rep-rate pulsed-power systems is also discussed.",
"URL": "http://ui.adsabs.harvard.edu/abs/2001JaJAP..40.1152O/abstract",
"title": "High-Repetition-Rate Electron-Beam-Pumped KrF Laser Technology for Inertial-Fusion-Energy Drivers",
"year_published": 2001,
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"Inertial frame of reference",
"Materials science",
"Laser power scaling",
"Fusion power",
"Laser technology",
"Laser",
"Diode",
"Cathode ray",
"Pulsed power"
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{
"abstract": "FAST is a new machine proposed to support ITER experimental exploitation as well as to anticipate DEMO relevant physics and technology. FAST is aimed at studying, under burning plasma relevant conditions, fast particle (FP) physics, plasma operations and plasma wall interaction in an integrated way. FAST has the capability to approach all the ITER scenarios significantly closer than the present day experiments using deuterium plasmas. The necessity of achieving ITER relevant performance with a moderate cost has led to conceiving a compact tokamak (R = 1.82m, a = 0.64m) with high toroidal field (BT up to 8.5T) and plasma current (Ip up to 8MA). In order to study FP behaviours under conditions similar to those of ITER, the project has been provided with a dominant ion cyclotron resonance heating system (ICRH; 30MW on the plasma). Moreover, the experiment foresees the use of 6MW of lower hybrid (LHCD), essentially for plasma control and for non-inductive current drive, and of electron cyclotron resonance heating (ECRH, 4MW) for localized electron heating and plasma control. The ports have been designed to accommodate up to 10MW of negative neutral beams (NNBI) in the energy range 0.5\u20101MeV. The total power input will be in the 30\u201040MW range under different plasma scenarios with a wall power load comparable to that of ITER ( P/ R\u223c 22MWm \u22121 ). All the ITER scenarios will be studied: from the reference H mode, with plasma edge and ELMs characteristics similar to the ITER ones (Q up to \u22481.5), to a full current drive scenario, lasting around 170s. The first wall (FW) as well as the divertor plates will be of tungsten in order to ensure reactor relevant",
"URL": "https://ui.adsabs.harvard.edu/abs/2010NucFu..50i5005P/abstract",
"title": "The Fusion Advanced Studies Torus (FAST): a proposal for an ITER satellite facility in support of the development of fusion energy",
"year_published": 2010,
"fields_of_study": [
"Tokamak",
"Nuclear engineering",
"Physics",
"Magnetic confinement fusion",
"Electron cyclotron resonance",
"Atomic physics",
"Ion cyclotron resonance",
"Fusion power",
"Divertor",
"Vacuum chamber",
"Plasma"
],
"first_author": "Aldo Pizzuto",
"scholarly_citations_count": 67,
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"sentence": "Moreover, the experiment foresees the use of 6MW of lower hybrid LHCD, essentially for plasma control and for non-inductive current drive, and of electron cyclotron resonance heating ECRH, 4MW for localized electron heating and plasma control.",
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"sentence": "The ports have been designed to accommodate up to 10MW of negative neutral beams NNBI in the energy range 0.51MeV.",
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"sentence": "The total power input will be in the 3040MW range under different plasma scenarios with a wall power load comparable to that of ITER P R 22MWm 1.",
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"sentence": "The first wall FW as well as the divertor plates will be of tungsten in order to ensure reactor relevant",
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{
"abstract": "2D arrays of laser diodes were developed and investigated under QCW operating conditions. Output power and energy density up to 1 kW/cm2 and 0.45 J/cm2 (at pulse duration 0.5 ms) were measured at the wavelength 810 nm. The spectral composition of radiation, shape of the output pulses, and far-field and near-field radiation zones were examined under various pumping parameters. The kinetics of the temperature profiles in monolithic QCW AlGaAs/GaAs linear bars and 2D arrays, emitting at the wavelength 810 nm was modeled numerically. Quasi-CW and CW operation under various pump parameters were considered as a function of a heat sink design. A calculation model was used to interpret the experimental dependences of the output parameters of the arrays on the pump conditions for application in the solid-state laser driver project. The limit of total power conversion efficiency of diode lasers was analyzed in respect of the threshold current density, series resistance and external differential quantum efficiency. The estimated maximum value of 75% was obtained for the present technological level of the diode lasers production. The corresponding limit of the output optical power density of 2D laser array was defined around 10 kW/cm2.",
"URL": "https://ui.adsabs.harvard.edu/abs/1999LPB....17..427B/abstract",
"title": "2D high power laser diode arrays for solid-state laser driver inertial fusion energy project",
"year_published": 1999,
"fields_of_study": [
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"Optics",
"Materials science",
"Laser power scaling",
"Energy conversion efficiency",
"Laser diode",
"Solid-state laser",
"Laser",
"Diode",
"Distributed feedback laser"
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{
"abstract": "Ultrafast, two-dimensional x-ray imaging is an important diagnostics for the inertial fusion energy research, especially in investigating implosion dynamics at the final stage of the fuel compression. Although x-ray radiography was applied to observing the implosion dynamics, intense x-rays emitted from the high temperature and dense fuel core itself are often superimposed on the radiograph. This problem can be solved by coupling the x-ray radiography with monochromatic x-ray imaging technique. In the experiment, 2.8 or 5.2 keV backlight x-rays emitted from laser-irradiated polyvinyl chloride or vanadium foils were selectively imaged by spherically bent quartz crystals with discriminating the out-of-band emission from the fuel core. This x-ray radiography system achieved 24\u2002\u03bcm and 100 ps of spatial and temporal resolutions, respectively.",
"URL": "https://inis.iaea.org/Search/search.aspx?orig_q=RN:44019222",
"title": "Monochromatic x-ray radiography for areal-density measurement of inertial fusion energy fuel in fast ignition experiment.",
"year_published": 2010,
"fields_of_study": [
"Inertial confinement fusion",
"Optics",
"Physics",
"Area density",
"Implosion",
"Fusion power",
"Industrial radiography",
"Monochromatic color",
"Plasma diagnostics",
"Nondestructive testing"
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"first_author": "Shinsuke Fujioka",
"scholarly_citations_count": 12,
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"abstract": "In the Earth\u2019s magnetosphere, sunspots and magnetic cusp fusion devices, the boundary between the plasma and the magnetic field is marked by a diamagnetic current layer with a rapid change in plasma pressure and magnetic field strength. First principles numerical simulations were conducted to investigate this boundary layer with a spatial resolution beyond electron gyroradius while incorporating a global equilibrium structure. The boundary layer thickness is discovered to be on the order of electron gyroradius scale due to a self-consistent electric field suppressing ion gyromotion at the boundary. Formed at the scale of the electron gyroradius, the electric field plays a critical role in determining equilibrium structure and plasma transport. The discovery highlights the necessity to incorporate electron gyroradius scale physics in studies aimed at advancing our understanding of fusion devices, the magnetosphere and sunspots.",
"URL": "https://www.frontiersin.org/articles/10.3389/fspas.2019.00074/full",
"title": "Discovery of an Electron Gyroradius Scale Current Layer: Its Relevance to Magnetic Fusion Energy, Earth's Magnetosphere and Sunspots",
"year_published": 2019,
"fields_of_study": [
"Boundary layer",
"Magnetic field",
"Physics",
"Magnetosphere",
"Electron",
"Boundary layer thickness",
"Computational physics",
"Electric field",
"Plasma",
"Gyroradius"
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"first_author": "Jaeyoung Park",
"scholarly_citations_count": 4,
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"abstract": "Experimental and numerical studies of the fluid dynamics of thin liquid film wall protection systems have been conducted in support of the ARIES-IFE study. Both the porous \u201cwetted wall\u201d concept, involving low-speed injection through a porous wall normal to the surface, and the \u201cforced film\u201d concept, involving high-speed injection through slots tangential to the surface, have been examined. These initial studies focus upon the \u201cpreshot\u201d feasibility of these concepts, between chamber clearing and the fusion event. For the wetted wall, a three-dimensional level contour reconstruction method was used to track the evolution of the liquid film on downward-facing walls for different initial conditions and liquid properties with evaporation and condensation at the free surface. The effects of these parameters on the film dynamics, the free surface topology, the frequency of liquid drop formation and detachment, the minimum film thickness between explosions, and the equivalent diameter of detached drops have been analyzed. Initial experimental results are in reasonable agreement with the numerical predictions. Generalized nondimensional charts for identifying appropriate \u201cdesign windows\u201d for successful operation of the wetted wall protection concept have been developed. The results demonstrate that a minimum repetition rate is required to avoid liquid dripping into the reactor cavity and that a minimum injection velocity is required in order to maintain a minimum film thickness over the first wall. For the forced film concept, experimental investigations of high-speed water films injected onto downwardfacing flat and curved surfaces at angles of inclination up to 45 deg below the horizontal were conducted. Mean detachment length and the lateral extent of the film were measured for a wide range of liquid-solid contact angles at different values of the initial film thickness, liquid injection speed, and surface orientation. The results show that the film detaches earlier (i.e., farther upstream) for nonwetting surfaces and for flat (versus curved) surfaces. The nonwetting flat surface data are therefore used to establish a conservative \u201cdesign window\u201d for film detachment. Initial observations of film flow around cylindrical obstacles suggest that cylindrical dams are incompatible with forced films.",
"URL": "https://www.researchgate.net/profile/Minami_Yoda/publication/237252742_An_Investigation_of_the_Fluid_Dynamics_Aspects_of_Thin_Liquid_Film_Protection_Schemes_for_Inertial_Fusion_Energy_Reactor_Chambers/links/54c665000cf256ed5a9e5f83.pdf",
"title": "An investigation of the fluid dynamics aspects of thin liquid film protection schemes for inertial fusion energy reactor chambers",
"year_published": 2004,
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"Hydraulic diameter",
"Free surface",
"Materials science",
"Condensation",
"Mechanics",
"Evaporation",
"Contact angle",
"Porosity",
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"first_author": "Minami Yoda",
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"abstract": "Exceptionally high reaction gains of hydrogen protons measured with the boron isotope 11 are compared with other fusion reactions. This is leading to the conclusion that secondary avalanche reactions are happening and confirming the results of high-gain, neutron-free, clean, safe, low-cost, and long-term available energy. The essential basis is the unusual non-thermal block-ignition scheme with picosecond laser pulses of extremely high powers above the petawatt range.",
"URL": "http://ui.adsabs.harvard.edu/abs/2015LPB....33..773H/abstract",
"title": "Fusion energy using avalanche increased boron reactions for block-ignition by ultrahigh power picosecond laser pulses",
"year_published": 2015,
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"Materials science",
"Isotopes of boron",
"Fusion power",
"Range (particle radiation)",
"Available energy",
"Optoelectronics",
"Boron",
"Hydrogen",
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"first_author": "Heinrich Hora",
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"abstract": "A parameter study of a proposed inertial fusion energy chamber is performed. A baseline case of a 6-m-radius chamber filled with 6 \u03bcg/cm3 of xenon is studied in detail. The maximum first-wall tempe...",
"URL": "http://www.ans.org/pubs/journals/fst/a_36197",
"title": "Parameter Study of an Inertial Fusion Energy Chamber Response Using the 1-D BUCKY Radiation Hydrodynamics Code",
"year_published": 2014,
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"Nuclear engineering",
"Physics",
"Code (cryptography)",
"Inertial frame of reference",
"Fusion power",
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"Xenon"
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"abstract": "Recent progress in surface instabilities of the Rayleigh-Taylor type at the ablative surface of laser-driven inertial fusion energy (IFE) target is reviewed with the objective of increasing the efficiency of IFE by reducing the growth rate of Rayleigh-Taylor Instability (RTI) using the following two mechanisms: (i) porous lining in the absence of electric force at the ablative surface of the IFE target, i.e. hydrodynamics and magnetohydrodynamics and (ii) porous lining of smart materials of nanostructure in the presence of electric force at the ablative surface of the IFE target, i.e. electrohydrodynamics. The former mechanism deals with two cases. Case 1 is the study of linear and nonlinear RTIs in an ordinary viscous fluid past a densely packed porous lining considering combined lubrication and Stokes approximations. Case 2 deals with RTI considering only Stokes approximation. Mechanism (ii) deals with RTI in a poorly conducting fluid in the presence of a transverse electric field called electrohydrodynamic RTI (ERTI). In both cases a simple theory based on replacing the no-slip condition with Saffman condition with and without thermal radiation is proposed. Both analytical and numerical techniques are used to study RTI. It is shown in both mechanisms, that the porous lining reduces the ratio of growth rates by about 80% compared to about 45% predicted in the literature, over the value that it would have if the target shell is bounded by an impermeable boundary. This finding is useful in the effective extraction of IFE by reducing the asymmetry caused by laser radiation in fusing deuterium-tritium in the target. These mechanisms are also useful in biomedical engineering problems in controlling the effects of plaques in coronary artery diseases and in trachea (i.e. wind pipe in the body).",
"URL": "http://eprints-bangaloreuniversity.in/1564/",
"title": "Electrohydrodynamic surface instabilities: Role of porous lining at the ablative surface of laser-driven inertial fusion energy target",
"year_published": 2007,
"fields_of_study": [
"Lubrication",
"Instability",
"Fusion power",
"Magnetohydrodynamics",
"Mechanics",
"Electric field",
"Viscous liquid",
"Thermal radiation",
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"abstract": "Despite several decades of dedicated R&D, fusion, a potentially world-changing energy source, remains decades away from commercialisation. The majority of development thus far has been via publicly-funded programmes led by government laboratories focused on scientific research and in which commercialisation strategy and innovation play a minor role. Generally, such programmes follow a linear model of innovation in which commercial aspects are not considered until later in development. In consequence and without intention, devices not well-suited for commercial application are being pursued. In recent years, however, privately funded fusion start-ups have emerged with the goal of accelerating the commercialisation of fusion. Fusion start-ups are, by necessity, operating on a fundamentally different model of innovation: agile innovation, whereby technology is developed flexibly and iteratively towards an explicit commercial goal. Technology Roadmapping is a method that has been effective for supporting agile innovation but thus far has had limited application to mission-led hardware development. We characterise the key features of the fusion innovation approach and create a novel Technology Roadmapping process for fusion start-ups, which is developed via a case study with Tokamak Energy Ltd. The main elements of the developed process, the resulting Technology Roadmap, and its impact are presented.",
"URL": "https://ideas.repec.org/a/eee/tefoso/v158y2020ics0040162519318281.html",
"title": "Technology Roadmapping for mission-led agile hardware development: a case study of a commercial fusion energy start-up",
"year_published": 2020,
"fields_of_study": [
"Agile software development",
"Government",
"Fusion power",
"Linear model of innovation",
"Technology roadmap",
"Energy source",
"Start up",
"Computer science",
"Process (engineering)",
"Computer hardware"
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"first_author": "Richard J. Pearson",
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"sentence": "In recent years, however, privately funded fusion start-ups have emerged with the goal of accelerating the commercialisation of fusion.",
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"sentence": "Fusion start-ups are, by necessity, operating on a fundamentally different model of innovation agile innovation, whereby technology is developed flexibly and iteratively towards an explicit commercial goal.",
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"sentence": "Technology Roadmapping is a method that has been effective for supporting agile innovation but thus far has had limited application to mission-led hardware development.",
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"sentence": "We characterise the key features of the fusion innovation approach and create a novel Technology Roadmapping process for fusion start-ups, which is developed via a case study with Tokamak Energy Ltd.",
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"abstract": "We have successfully demonstrated a large aperture 803 nm AlGaAs diode laser module as a pump source for a 1053 nm, 10 J output Nd:glass slab laser amplifier for diode-pumped solid-state laser (DPSSL) fusion driver. Detailed performance results of the laser diode module are presented, including bar package and stack configuration, and their thermal design and analysis. A sufficiently low thermal impedance of the stack was realized by combining backplane liquid cooling configuration with modular bar package architecture. Total peak power of 110 kW and electrical to optical conversion efficiency of 46% were obtained from the module consisting of a total of 1000 laser diode bars. A peak intensity of 2.6 kW/cm2 was accomplished across an emitting area of 418 mm\u00d710 mm. Currently, this laser diode array module with a large two-dimensional aperture is, to our knowledge, the only operational pump source for the high output energy DPSSL.",
"URL": "http://iopscience.iop.org/article/10.1143/JJAP.40.6852/pdf",
"title": "Quasi-CW 110 kW AlGaAs laser diode array module for inertial fusion energy laser driver",
"year_published": 2001,
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"Laser power scaling",
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"first_author": "Toshiyuki Kawashima",
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"abstract": "We present the results of performance modeling of diode-pumped solid state laser beamlines designed for use in Laser Inertial Fusion Energy (LIFE) power plants. Our modeling quantifies the efficiency increases that can be obtained by increasing peak diode power and reducing pump-pulse duration, to reduce decay losses. At the same efficiency, beamlines that use laser slabs of Yb:YAG or Yb:S-FAP require lower diode power than beamlines that use laser slabs of Nd:phosphate glass, since Yb:YAG and Yb:S-FAP have longer storage lifetimes. Beamlines using Yb:YAG attain their highest efficiency at a temperature of about 200K. Beamlines using Nd:phosphate glass or Yb:S-FAP attain high efficiency at or near room temperature.",
"URL": "https://www.researchgate.net/profile/Charles_Boley/publication/263766305_Comparison_of_Ndphosphate_glass_YbYAG_and_YbS-FAP_laser_beamlines_for_laser_inertial_fusion_energy_(LIFE)_Invited/links/54010dd90cf2c48563aeedcc.pdf",
"title": "Comparison of Nd:phosphate glass, Yb:YAG and Yb:S-FAP laser beamlines for laser inertial fusion energy (LIFE) [Invited]",
"year_published": 2011,
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"Materials science",
"Laser Inertial Fusion Energy",
"Solid-state laser",
"Phosphate glass",
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"first_author": "Alvin C. Erlandson",
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"abstract": "This paper is a complement to our previous work [Jpn. J. Appl. Phys. 46 (2007) 6000] on the accuracy of the position measurement method using an Arago spot for an inertial fusion energy target tracking system and we here report an improvement of the measurement accuracy using a divergent laser beam. By employing divergent beam illumination, we can magnify the displacement of the Arago spot compared with the actual displacement of the target without enlarging the diameter of the Arago spot significantly, allowing us to measure the small displacement of the target with high accuracy over a large measurement range. The experimental results for a 5-mm-diameter target demonstrated that a measurement accuracy of lower than 0.2 \u00b5m can be achieved when the distance between the target and a charge-coupled device camera is within the range from 2 to 10 m.",
"URL": "http://ci.nii.ac.jp/naid/150000050119",
"title": "Position Measurement Method Using a Divergent Laser Beam and Arago Spot for Tracking of an Inertial Fusion Energy Target",
"year_published": 2008,
"fields_of_study": [
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"Physics",
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"first_author": "Koichi Saruta",
"scholarly_citations_count": 6,
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"abstract": "The Electra laser system is currently being developed at the Naval Research Laboratory to serve as a test bed for laser driver technologies needed for an inertial fusion energy power plant. The main amplifier has produced 730 J of laser light operating in an oscillator mode. These results as well as advancement of the laser physics, electron beam deposition, and the pulse power technologies give us projections of >7% wall plug efficiency for an IFE system. The Electra main amplifier in oscillator configuration has run continuously at 1 Hz, 2.5 Hz, and 5 Hz for multi-thousand shot runs. This paper will discuss recent results of the Electra program at the Naval Research Laboratory including integrating the Electra main amplifier into a complete laser amplifier system. Issues addressed will include development paths for the cathode, window coating, and foil longevity to attain the durability required for a fusion power plant.",
"URL": "https://www.ans.org/pubs/journals/fst/a_1528",
"title": "Development of a Continuous Multi-Thousand Shot Electron Beam Pumped KrF Rep-Rate Laser for Fusion Energy",
"year_published": 2007,
"fields_of_study": [
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"Nuclear physics",
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"Wall-plug efficiency",
"Laser science",
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"first_author": "Patrick M. Burns",
"scholarly_citations_count": 8,
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{
"abstract": "Most radionuclide generation/depletion codes consider only neutron reactions and assume that charged particles, which may be generated in these reactions, deposit their energy locally without undergoing further nuclear interactions. Neglect of sequential charged-particle (x,n) reactions can lead to large underestimation in the inventories of radionuclides. PCROSS code was adopted for use with the ACAB activation code to enable calculation of the effects of (x,n) reactions upon radionuclide inventories and inventory-related indices. Activation calculations were made for Flibe (2LiF + BeF{sub 2}) coolant in the HYLIFE-II inertial fusion energy (IFE) power plant design. For pure Flibe coolant, it was found that (x,n) reactions dominate the residual contact dose rate at times of interest for maintenance and decommissioning. For impure Flibe, however, radionuclides produced directly in neutron reaction dominate the contact dose rate and (x,n) reactions do not make a significant contribution. Results demonstrate potential importance of (x,n) reactions and that the relative importance of (x,n) reactions varies strongly with the composition of the material considered. Future activation calculations should consider (x,n) reactions until a method for pre-determining their importance is established.",
"URL": "https://ans.org/pubs/journals/fst/a_43018",
"title": "Sequential Charged-Particle and Neutron Activation of Flibe in the Hylife-II Inertial Fusion Energy Power Plant Design",
"year_published": 1996,
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"first_author": "Jeffery F. Latkowski",
"scholarly_citations_count": 5,
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"sentence": "Activation calculations were made for Flibe 2LiF BeF coolant in the HYLIFE-II inertial fusion energy IFE power plant design.",
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{
"abstract": "High specification, polymer capsules, to produce inertial fusion energy targets, were continuously fabricated using surfactant-free, inertial centralisation, and ultrafast polymerisation, in a scalable flow reactor. Laser-driven, inertial confinement fusion depends upon the interaction of high-energy lasers and hydrogen isotopes, contained within small, spherical and concentric target shells, causing a nuclear fusion reaction at ~150\u2009M\u00b0C. Potentially, targets will be consumed at ~1\u2009M per day per reactor, demanding a 5000x unit cost reduction to ~$0.20, and is a critical, key challenge. Experimentally, double emulsions were used as templates for capsule-shells, and were formed at 20\u2009Hz, on a fluidic chip. Droplets were centralised in a dynamic flow, and their shapes both evaluated, and mathematically modeled, before subsequent shell solidification. The shells were photo-cured individually, on-the-fly, with precisely-actuated, millisecond-length (70\u2009ms), uniform-intensity UV pulses, delivered through eight, radially orchestrated light-pipes. The near 100% yield rate of uniform shells had a minimum 99.0% concentricity and sphericity, and the solidification processing period was significantly reduced, over conventional batch methods. The data suggest the new possibility of a continuous, on-the-fly, IFE target fabrication process, employing sequential processing operations within a continuous enclosed duct system, which may include cryogenic fuel-filling, and shell curing, to produce ready-to-use IFE targets.",
"URL": "https://orca.cardiff.ac.uk/101903/",
"title": "Continuous and scalable polymer capsule processing for inertial fusion energy target shell fabrication using droplet microfluidics",
"year_published": 2017,
"fields_of_study": [
"Inertial confinement fusion",
"Nuclear engineering",
"Fluidics",
"Fabrication",
"Sphericity",
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"first_author": "Jin Li",
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{
"sentence": "Droplets were centralised in a dynamic flow, and their shapes both evaluated, and mathematically modeled, before subsequent shell solidification.",
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"sentence": "The shells were photo-cured individually, on-the-fly, with precisely-actuated, millisecond-length 70 ms, uniform-intensity UV pulses, delivered through eight, radially orchestrated light-pipes.",
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"sentence": "The data suggest the new possibility of a continuous, on-the-fly, IFE target fabrication process, employing sequential processing operations within a continuous enclosed duct system, which may include cryogenic fuel-filling, and shell curing, to produce ready-to-use IFE targets.",
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{
"abstract": "The fusion event in inertial fusion energy (IFE) reactors creates neutrons, photons, and charged particles that can damage the chamber first walls. The Prometheus design study used a high-speed thin film of molten lead injected tangential to the wall to protect the upper endcap of the reactor chamber from damaging X rays and target debris. To assure full chamber coverage, the film must remain attached. Film detachment under the influence of gravity is most likely to occur on the downward-facing surfaces over the upper endcap of the reactor chamber. Accurate numerical predictions of detachment length are effectively impossible in this turbulent flow because of difficulties in determining appropriate boundary conditions near the detachment point.As part of the ARIES-IFE study, experimental investigations of high-speed water films injected onto downward-facing planar surfaces at angles of inclination up to 45 deg below the horizontal were therefore performed. The initial growth and subsequent detachment of films with initial thickness up to 2 mm and injection speed up to 11 m/s were measured. To our knowledge, these experiments are the first to investigate the detachment of turbulent liquid films on downward-facing surfaces. The implications of these initial results on thin liquid protection and the 'wetmore\u00a0\u00bb wall' concept are discussed.\u00ab\u00a0less",
"URL": "http://www.osti.gov/scitech/biblio/20845908",
"title": "Experimental Studies of High-Speed Liquid Films on Downward-Facing Surfaces for Inertial Fusion Energy Wet Wall Concepts",
"year_published": 2003,
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"abstract": "An overview of the developments postcirca 1980s in the instrumentation and application of charge exchange neutral particle diagnostics on magnetic fusion energy experiments is presented. First, spectrometers that employ only electric fields and hence provide ion energy resolution but not mass resolution are discussed. Next, spectrometers that use various geometrical combinations of both electric and magnetic fields to provide both energy and mass resolutions are reviewed. Finally, neutral particle diagnostics based on utilization of time-of-flight techniques are presented.",
"URL": "https://core.ac.uk/display/86174476",
"title": "Invited Review Article: Contemporary instrumentation and application of charge exchange neutral particle diagnostics in magnetic fusion energy experiments",
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"abstract": "A high-energy, high beam quality, diode-pumped 1053-nm Nd:silica-phosphate glass laser amplifier has been designed, constructed and tested in order to verify the conceptual design of HALNA (high average-power laser for nuclear-fusion application): a diode-pumped solid-state laser based on a water-cooled zig-zag slab optical geometry. This amplifier yields an 8.5 J output energy per pulse at 0.5 Hz in a 20 ns pulse of two times the diffraction limit beam quality with an optical-to-optical conversion efficiency of 10.9%. This is the first demonstration of a diode-pumped solid-state laser amplifier for the inertial fusion energy (IFE) driver. The detailed considerations on the optical and thermal designs of the novel amplifier architecture are discussed. The experimental results revealed that the primary requirements for the IFE driver, such as diode-pumping, energy storage and extraction efficiencies, and beam quality have been fulfilled.",
"URL": "http://iopscience.iop.org/article/10.1143/JJAP.40.6415/pdf",
"title": "Design and Performance of a Diode-Pumped Nd:Silica-Phosphate Glass Zig-Zag Slab Laser Amplifier for Inertial Fusion Energy",
"year_published": 2001,
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"Energy conversion efficiency",
"Fusion power",
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"first_author": "Toshiyuki Kawashima",
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"abstract": "Parametric system studies of an inertial confinement fusion (ICF) reactor system to transmute fission products from an LWR economy have been carried out. The ICF reactors would produce net power in addition to transmuting fission products. The particular ICF concept examined is an impact fusion approach termed HYPERFUSE, in which hypervelocity pellets, traveling on the order of 100 to 300 km/sec, collide with a target in a reactor chamber and initiate a thermonuclear reaction. The DT fusion fuel is contained in a shell of the material to be transmuted, e.g., /sup 137/Cs or /sup 90/Sr. The 14 MeV fusion neutrons released during the pellet burn cause transmutation reactions (e.g., (n, 2n), (n, ..cap alpha..), etc.) that convert the long lived fission products (FP's) either to stable products or to species that decay with a short half-life to a stable product.",
"URL": "https://www.osti.gov/servlets/purl/5551125/",
"title": "Hyper-fuse: a novel inertial confinement system utilizing hypervelocity projectiles for fusion energy production and fission waste transmutation",
"year_published": 1979,
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"Boosted fission weapon",
"Nuclear physics",
"Materials science",
"Fusion power",
"Muon-catalyzed fusion",
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"first_author": "H. Makowitz",
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"abstract": "The current fusion energy development path, based on large volume moderate magnetic B field devices is proving to be slow and expensive. A modest development effort in exploiting new superconductor magnet technology development, and accompanying plasma physics research at high-B, could open up a viable and attractive path for fusion energy development. This path would feature smaller volume, fusion capable devices that could be built more quickly than low-to-moderate field designs based on conventional superconductors. Fusion\u2019s worldwide development could be accelerated by using several small, flexible devices rather than relying solely on a single, very large device. These would be used to obtain the acknowledged science and technology knowledge necessary for fusion energy beyond achievement of high gain. Such a scenario would also permit the testing of multiple confinement configurations while distributing technical and scientific risk among smaller devices. Higher field and small size also allows operation away from well-known operational limits for plasma pressure, density and current. The advantages of this path have been long recognized\u2014earlier US plans for burning plasma experiments (compact ignition tokamak, burning plasma experiment, fusion ignition research experiment) featured compact high-field designs, but these were necessarily pulsed due to the use of copper coils. Underpinning this new approach is the recent industrial maturity of high-temperature, high-field superconductor tapes that would offer a truly \u201cgame changing\u201d opportunity for magnetic fusion when developed into large-scale coils. The superconductor tape form and higher operating temperatures also open up the possibility of demountable superconducting magnets in a fusion system, providing a modularity that vastly improves simplicity in the construction, maintenance, and upgrade of the coils and the internal nuclear engineering components required for fusion\u2019s development. Our conclusion is that while tradeoffs exist in design choices, for example coil, cost and stress limits versus size, the potential physics and technology advantages of high-field superconductors are attractive and they should be vigorously pursued for magnetic fusion\u2019s development.",
"URL": "https://cyberleninka.org/article/n/873481",
"title": "Smaller & Sooner: Exploiting High Magnetic Fields from New Superconductors for a More Attractive Fusion Energy Development Path",
"year_published": 2016,
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"first_author": "Dennis G. Whyte",
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"abstract": "Power flow in a recyclable transmission line (RTL) for a z-pinch-driven inertial-confinement fusion energy (IFE) system is studied. In a magnetically insulated transmission line, plasma forms by explosive emission on the cathode but emission from the anode does not occur. However, in an RTL, the large linear current density that flows in the electrodes at small radius near the load resistively heats the anode surface, leading to anode plasma formation and ion emission. If the impedance of the RTL is too small, large ion current losses can occur and large electron flow currents can be launched into the z-pinch load region. If only the boundary current drives the z-pinch load, then these large electron flow currents can introduce a polarity effect with more bound current in the anode than the cathode. While being mindful of the IFE system requirement to maintain a small RTL inductance, these problems are avoided by choosing the line impedance at the load end of the RTL to be well above the effective impedance of the imploding load. In this case, the ion current losses are tolerable and the electron flow current is negligibly small. For the present baseline design with a peak current of 60 MA driving a 100-ns implosion, these power flow constraints require a gap of order 2 mm or more at the load end of the RTL",
"URL": "https://www.infona.pl/resource/bwmeta1.element.ieee-art-000004032905",
"title": "Power Flow in a Magnetically Insulated Recyclable Transmission Line for a Z -Pinch-Driven Inertial-Confinement-Fusion Energy System",
"year_published": 2006,
"fields_of_study": [
"Electrical engineering",
"Electric power transmission",
"Electrical impedance",
"Materials science",
"Implosion",
"Current density",
"Ion current",
"Z-pinch",
"Cathode",
"Mechanics",
"Anode"
],
"first_author": "Joseph W. Schumer",
"scholarly_citations_count": 21,
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"sentence": "While being mindful of the IFE system requirement to maintain a small RTL inductance, these problems are avoided by choosing the line impedance at the load end of the RTL to be well above the effective impedance of the imploding load.",
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"category": "Nuclear Fusion Technique",
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"sentence": "For the present baseline design with a peak current of 60 MA driving a 100-ns implosion, these power flow constraints require a gap of order 2 mm or more at the load end of the RTL",
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{
"abstract": "Abstract If the costing assumptions upon which the positive assessment of conventional large superconducting fusion reactors are based proves overly optimistic, approaches that promise considerably increased system power density and reduced mass utilization will be required. These more compact reactor embodiments generally must operate with reduced shield thickness and resistive magnets. Because of the unique magnetic topology associated with the Reversed-Field Pinch (RFP), the compact reactor embodiment for this approach is particularly attractive from the viewpoint of low-field resistive coils operating with ohmic losses that can be made small relative to the fusion power. The RFP, therefore, is used as one example of a high-power-density (HPD) approach to magnetic fusion energy. A comprehensive system model is described and applied to select a unique, cost-optimized design point that will be used for a subsequent conceptual engineering design of the compact RFP Reactor (CRFPR). This cost-optimized CRFPR design serves as an example of a HPD fusion reactor that would operate with system power densities and mass utilizations that are comparable to fission power plants, these measures of system performance being an order of magnitude more favorable than the conventional approaches to magnetic fusion energy (MFE).",
"URL": "https://inis.iaea.org/Search/search.aspx?orig_q=RN:14721948",
"title": "High-power-density approaches to magnetic fusion energy: problems and promise of compact Reversed-Field Pinch Reactors (CRFPR)",
"year_published": 1983,
"fields_of_study": [
"Nuclear engineering",
"Physics",
"Pinch",
"Power (physics)",
"Magnet",
"Power density",
"Electromagnetic shielding",
"Fusion power",
"Reversed field pinch",
"Resistive touchscreen"
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"first_author": "Randy L. Hagenson",
"scholarly_citations_count": 2,
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"sentence": "Because of the unique magnetic topology associated with the Reversed-Field Pinch RFP, the compact reactor embodiment for this approach is particularly attractive from the viewpoint of low-field resistive coils operating with ohmic losses that can be made small relative to the fusion power.",
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"sentence": "This cost-optimized CRFPR design serves as an example of a HPD fusion reactor that would operate with system power densities and mass utilizations that are comparable to fission power plants, these measures of system performance being an order of magnitude more favorable than the conventional approaches to magnetic fusion energy MFE.",
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},
{
"abstract": "We have proposed and designed a laser-diode-pumped laser driver for inertial fusion energy (IFE) which consists of water-cooled zig-zag path Nd: glass (HAP-4) slab amplifiers. A driver module was designed under the several operational constraints and has 10 kJ total output energy at 351 nm and operates at 12 Hz with 9-12% overall efficiency. The laser driver producing 4 MJ blue output for IFE will consist of 400 modules",
"URL": "http://joi.jlc.jst.go.jp/JST.Journalarchive/lsj1973/28.176?from=CrossRef",
"title": "Conceptual Design of Laser-Diode-Pumped Water-Cooled Nd: Glass Slab Laser Driver for Inertial Fusion Energy",
"year_published": 2000,
"fields_of_study": [
"Slab",
"Conceptual design",
"Optics",
"Inertial frame of reference",
"Energy (signal processing)",
"Materials science",
"Amplifier",
"Fusion power",
"Laser diode",
"Laser"
],
"first_author": "Hiroki Matsui",
"scholarly_citations_count": 3,
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{
"abstract": "We examine the potential that imposed magnetic fields of tens of Tesla that increase to greater than 10 kT (100 MGauss) under implosion compression may relax the conditions required for ignition and propagating burn in indirect-drive inertial confinement fusion (ICF) targets. This may allow the attainment of ignition, or at least significant fusion energy yields, in presently performing ICF targets on the National Ignition Facility (NIF) that today are sub-marginal for thermonuclear burn through adverse hydrodynamic conditions at stagnation [Doeppner et al., Phys. Rev. Lett. 115, 055001 (2015)]. Results of detailed two-dimensional radiation-hydrodynamic-burn simulations applied to NIF capsule implosions with low-mode shape perturbations and residual kinetic energy loss indicate that such compressed fields may increase the probability for ignition through range reduction of fusion alpha particles, suppression of electron heat conduction, and potential stabilization of higher-mode Rayleigh-Taylor instabilities. Optimum initial applied fields are found to be around 50\u2009T. Given that the full plasma structure at capsule stagnation may be governed by three-dimensional resistive magneto-hydrodynamics, the formation of closed magnetic field lines might further augment ignition prospects. Experiments are now required to further assess the potential of applied magnetic fields to ICF ignition and burn on NIF.",
"URL": "https://ui.adsabs.harvard.edu/abs/2017PhPl...24f2708P/abstract",
"title": "The potential of imposed magnetic fields for enhancing ignition probability and fusion energy yield in indirect-drive inertial confinement fusion",
"year_published": 2017,
"fields_of_study": [
"Inertial confinement fusion",
"Physics",
"Ignition system",
"Magnetic confinement fusion",
"Nuclear physics",
"Implosion",
"Fusion power",
"National Ignition Facility",
"Mechanics",
"Thermonuclear fusion",
"Plasma"
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"first_author": "L. J. Perkins",
"scholarly_citations_count": 68,
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{
"abstract": "Abstract Traditionally, waste management studies for fusion energy have used the waste disposal rating (WDR) to evaluate if radioactive material from irradiated structures could qualify for shallow land burial. However, given the space limitations and the negative public perception of large volumes of waste, there is a growing international motivation to develop a fusion waste management system that maximizes the amount of material that can be cleared or recycled. In this work, we present an updated assessment of the waste management options for the HYLIFE-II inertial fusion energy (IFE) power plant, using the concept of clearance index (CI) for radioactive waste disposal. With that purpose, we have performed a detailed neutronics analysis of the HYLIFE-II design, using the tart and acab computer codes for neutron transport and activation, respectively. Whereas the traditional version of acab only provided the user with the \u03b3 contact dose rate for recycling assessments and WDR as an index for waste disposal considerations, here we have modified the code to calculate CIs using the current international atomic energy agency (IAEA) clearance limits for radiological waste disposal. The results from the analysis are used to perform an assessment of the waste management options for the HYLIFE-II IFE design.",
"URL": "https://www.osti.gov/servlets/purl/15013324/",
"title": "Use of clearance indexes to assess waste disposal issues for the HYLIFE-II inertial fusion energy power plant design",
"year_published": 2002,
"fields_of_study": [
"Work (electrical)",
"Fusion power",
"Dose rate",
"Waste disposal",
"Environmental science",
"Power station",
"Nuclear reactor",
"Waste management",
"Neutron transport",
"Radioactive waste"
],
"first_author": "Susana Reyes",
"scholarly_citations_count": 8,
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{
"abstract": "Energy production by laser driven fusion energy is highly matured by spherical compression and ignition of deuteriumtritium (DT) fuel. An alternative scheme is the fast ignition where petawatt (PW)-picosecond (ps) laser pulses are used. A significant anomaly was measured and theoretically analyzed with very clean PW-ps laser pulses for avoiding relativistic self focusing. This permits a come-back of the side-on ignition scheme of uncompressed solid DT, which is in essential contrast to the spherical compression scheme. The conditions of side-on ignition thresholds needed exorbitantly high energy flux densities E*. These conditions are now in reach by using PW-ps laser pulses to verify side-on ignition for DT. Generalizing this to side-on igniting solid state density proton-Boron-11 (HB11) arrives at the surprising result that this is one order of magnitude more difficult than the DT fusion. This is in contrast to the well known impossibility of igniting HB11 by spherical laser compression and may offer fusion energy production with exclusion of neutron generation and nuclear radiation effects with a minimum of heat pollution in power stations and application for long mission space propulsion.",
"URL": "https://www.researchgate.net/profile/Babak_Malekynia2/publication/228628966_Nonlinear_force_driven_plasma_blocks_igniting_solid_density_hydrogen_boron_Laser_fusion_energy_without_radioactivity/links/00b495396ce8955b56000000.pdf",
"title": "Nonlinear force driven plasma blocks igniting solid density hydrogen boron: Laser fusion energy without radioactivity",
"year_published": 2009,
"fields_of_study": [
"Minimum ignition energy",
"Inertial confinement fusion",
"Fusion ignition",
"Ignition system",
"Atomic physics",
"Materials science",
"Fusion power",
"Self-focusing",
"Laser",
"Plasma"
],
"first_author": "H. Hora",
"scholarly_citations_count": 24,
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"sentence": "Generalizing this to side-on igniting solid state density proton-Boron-11 HB11 arrives at the surprising result that this is one order of magnitude more difficult than the DT fusion.",
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"abstract": "This paper investigates the use of the small-punch (SP) test to estimate the elastic-plastic fracture toughness (JIC) of structural alloys and weldments for superconducting magnets in fusion energy systems. SP testing was performed with thin-plate specimens of 10\u00d710\u00d70.5mm at liquid helium temperature (4K). Correlations between SP energy, equivalent fracture strain, and JIC were assessed. All JIC data were obtained using 25-mm-thick compact specimens that followed the standard test method for JIC. Finite element analysis was also performed to convert the experimentally measured load-displacement data into useful engineering information. The criterion for fracture used is the strain-energy density (strain energy absorbed per unit volume) required to produce crack initiation in a solid, uncracked specimen. The fracture strain-energy density was calculated and correlated with JIC.",
"URL": "https://ci.nii.ac.jp/naid/130003673246",
"title": "Cryogenic Fracture Toughness Evaluation of Structural Alloys and Weldments for Superconducting Magnets in Fusion Energy Systems by Small-punch Testing",
"year_published": 1999,
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"Fusion power",
"Austenitic stainless steel",
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"first_author": "Yasuhide Shindo",
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"abstract": "Intense light-ion beams are being developed for investigations of inertial confinement fusion (ICF). This effort has concentrated on developing the Particle Beam Fusion Accelerator II (PBFA II) at Sandia as a driver for ICF target experiments, on design concepts for a high-yield, high-gain Laboratory Microfusion Facility (LMF), and on a comprehensive system study of a light-ion beam-driven commercial fusion reactor (LIBRA). This article reports on the status of design concepts and research in these areas.",
"URL": "https://ui.adsabs.harvard.edu/abs/1993LPB....11..423R/abstract",
"title": "Intense light-ion beams provide a robust, common-driver path toward ignition, gain, and commercial fusion energy",
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"Fusion power",
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"abstract": "The current fusion energy development path, based on large volume moderate magnetic B field devices is proving to be slow and expensive. A modest development effort in exploiting new superconductor magnet technology development, and accompanying plasma physics research at high-B, could open up a viable and attractive path for fusion energy development. This path would feature smaller volume, fusion capable devices that could be built more quickly than low-to-moderate field designs based on conventional superconductors. Fusion\u2019s worldwide development could be accelerated by using several small, flexible devices rather than relying solely on a single, very large device. These would be used to obtain the acknowledged science and technology knowledge necessary for fusion energy beyond achievement of high gain. Such a scenario would also permit the testing of multiple confinement configurations while distributing technical and scientific risk among smaller devices. Higher field and small size also allows operation away from well-known operational limits for plasma pressure, density and current. The advantages of this path have been long recognized\u2014earlier US plans for burning plasma experiments (compact ignition tokamak, burning plasma experiment, fusion ignition research experiment) featured compact high-field designs, but these were necessarily pulsed due to the use of copper coils. Underpinning this new approach is the recent industrial maturity of high-temperature, high-field superconductor tapes that would offer a truly \u201cgame changing\u201d opportunity for magnetic fusion when developed into large-scale coils. The superconductor tape form and higher operating temperatures also open up the possibility of demountable superconducting magnets in a fusion system, providing a modularity that vastly improves simplicity in the construction, maintenance, and upgrade of the coils and the internal nuclear engineering components required for fusion\u2019s development. Our conclusion is that while tradeoffs exist in design choices, for example coil, cost and stress limits versus size, the potential physics and technology advantages of high-field superconductors are attractive and they should be vigorously pursued for magnetic fusion\u2019s development.",
"URL": "https://dspace.mit.edu/handle/1721.1/105878",
"title": "Smaller & Sooner: Exploiting High Magnetic Fields from New Superconductors for a More Attractive Fusion Energy Development Path",
"year_published": 2016,
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"abstract": "Abstract\n This paper analyses how a forced transition to low-carbon energy impacts the innovation of new energy technologies. We apply the insights to nuclear fusion, potentially a large provider of carbon-free energy currently attracting billions in private investments. We discuss the \u2018fastest-feasible-growth (FFG)\u2019-curve for transitions: exponential growth followed by linear growth, where the rate of latter is limited by the inverse lifetime of the installation. We analyse how innovation is affected if, during rapid deployment, a technology progresses through several generations. We identify key timescales: the learning time, the generation time, the build time, and the exponential growth time of the early deployment phase and compare these for different energy technologies. We distinguish learning rate-limited and generation-time-limited innovation. Applying these findings to fusion energy, we find that a long build time may slow deployment, slow learning, and promote early technology lock-in. Slow learning can be remedied by developing multiple concepts in parallel. Probabilistic analysis of value implies that the optimal strategy is to parallelise the development of many concepts. This concurs with the present surge in private investment in multiple concepts. For this strategy to be successful, the build time of the power plant must be minimized. This requirement favours concepts that lend themselves to modularisation and parallelisation of production and assembly.",
"URL": "NaN",
"title": "The interplay of the innovation cycle, build time, lifetime and deployment rate of new energy technologies. A case study of nuclear fusion energy",
"year_published": 2024,
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"first_author": "N J Lopes Cardozo",
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{
"abstract": "Under fusion reactor conditions, large quantities of irradiation defects and transmutation gases are produced per unit time by neutrons, resulting in accelerated degradation of structural candidate ferritic (F) and ferritic/martensitic (F/M) steels. Due to the lack of a suitable fusion neutron testing facility, we must rely on high-dose-rate ion-beam experiments and present-day crude modeling estimates. Of particular interest is the possibility of synergistic (positive feedback) effects on materials properties due to the simultaneous action of He, H, and displacement damage (dpa) during operation. In this paper we discuss the state-of-the-art in terms of the experimental understanding of synergistic effects and carry out simulations of triple-species irradiation under ion-beam conditions using first-of-its-kind modeling techniques. Although, state-of-the-art modeling and simulation is not sufficiently well developed to shed light on the experimental uncertainties, we are able to conclude that it is not clear whether synergistic effects, the evidence of which is still not conclusive, will ultimately play a critical role in material performance under fusion energy conditions. We review here some of the evidence for the synergistic effects of hydrogen in the presence of helium and displacement damage, and also include some recent data from our research. While the experimental results to date suggest possible mechanisms for the observed synergistic effects, it is only with more advanced modeling that we can hope to understand the details underlying the experimental observations. By employing modeling and simulation we propose an interaction model that is qualitatively consistent with experimental observations of dpa/He/H irradiation behavior. Our modeling, the results of which should be helpful to researchers going forward, points to gaps and voids in the current understanding of triple ion-beam irradiation effects (displacement damage produced simultaneously with helium and hydrogen implantation) and the synergistic effects of hydrogen.",
"URL": "https://escholarship.org/content/qt97d462x2/qt97d462x2.pdf",
"title": "A review of helium-hydrogen synergistic effects in radiation damage observed in fusion energy steels and an interaction model to guide future understanding",
"year_published": 2015,
"fields_of_study": [
"Irradiation",
"Nuclear engineering",
"Neutron",
"Radiation damage",
"Modeling and simulation",
"Nanotechnology",
"Materials science",
"Fusion power",
"Interaction model",
"Hydrogen",
"Helium"
],
"first_author": "Jaime Marian",
"scholarly_citations_count": 62,
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"sentence": "Although, state-of-the-art modeling and simulation is not sufficiently well developed to shed light on the experimental uncertainties, we are able to conclude that it is not clear whether synergistic effects, the evidence of which is still not conclusive, will ultimately play a critical role in material performance under fusion energy conditions.",
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"sentence": "We review here some of the evidence for the synergistic effects of hydrogen in the presence of helium and displacement damage, and also include some recent data from our research.",
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"abstract": "Some years ago it was suggested that halogen negative ions [1] could offer a feasible alternative path to positive ions as a heavy ion fusion driver beam which would not suffer degradation due to electron accumulation in the accelerator and beam transport system, and which could be converted to a neutral beam by photodetachment near the chamber entrance if desired. Since then, experiments have demonstrated that negative halogen beams can be extracted and accelerated away from the gas plume near the source with a surviving current density close to what could be achieved with a positive ion of similar mass, and with comparable optical quality. In demonstrating the feasibility of halogen negative ions as heavy ion driver beams, ion - ion plasmas, an interesting and somewhat novel state of matter, were produced. These plasmas, produced near the extractor plane of the sources, appear, based upon many lines of experimental evidence, to consist of almost equal densities of positive and negative chlorine ions, with only a small component of free electrons. Serendipitously, the need to extract beams from this plasma for driver development provides a unique diagnostic tool to investigate the plasma, since each component - positive ions, negative ions, and electrons -- can be extracted and measured separately. We discuss the relevance of these observations to understanding negative ion beam extraction from electronegative plasmas such as halogens, or the more familiar hydrogen of magnetic fusion ion sources. We suggest a concept which might improve negative hydrogen extraction by the addition of a halogen. The possibility and challenges of producing ion-ion plasmas with thin targets of halogens or, perhaps, salt, is briefly addressed.",
"URL": "https://escholarship.org/uc/item/8cp6t4sz.pdf",
"title": "Perspective on the Role of Negative Ions and Ion-Ion Plasmas in Heavy Ion Fusion Science, Magnetic Fusion Energy, and Related Fields",
"year_published": 2008,
"fields_of_study": [
"State of matter",
"Ion gun",
"Ion",
"Electron",
"Beam (structure)",
"Atomic physics",
"Chemistry",
"Hydrogen",
"Plasma",
"Free electron model"
],
"first_author": "L. Grisham and J.W. Kwan",
"scholarly_citations_count": 5,
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"sentence": "These plasmas, produced near the extractor plane of the sources, appear, based upon many lines of experimental evidence, to consist of almost equal densities of positive and negative chlorine ions, with only a small component of free electrons.",
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{
"abstract": "Abstract Some years ago it was suggested that halogen negative ions [L.R. Grisham, Nuclear Instruments and Methods in Physics Research A 464 (2001) 315] could offer a feasible alternative path to positive ions as a heavy ion fusion driver beam, which would not suffer degradation due to electron accumulation in the accelerator and beam transport system, and which could be converted to a neutral beam by photodetachment near the chamber entrance if desired. Since then, experiments have demonstrated that negative halogen beams can be extracted and accelerated away from the gas plume near the source with a surviving current density close to what could be achieved with a positive ion of similar mass, and with comparable optical quality. In demonstrating the feasibility of halogen negative ions as heavy ion driver beams, ion\u2013ion plasmas, an interesting and somewhat novel state of matter, were produced. These plasmas, produced near the extractor plane of the sources, appear, based upon many lines of experimental evidence, to consist of almost equal densities of positive and negative chlorine ions, with only a small component of free electrons. Serendipitously, the need to extract beams from this plasma for driver development provides a unique diagnostic tool to investigate the plasma, since each component \u2013 positive ions, negative ions, and electrons \u2013 can be extracted and measured separately. We discuss the relevance of these observations to understanding negative ion beam extraction from electronegative plasmas such as halogens, or the more familiar hydrogen of magnetic fusion ion sources. We suggest a concept that might improve negative hydrogen extraction by the addition of a halogen. The possibility and challenges of producing ion\u2013ion plasmas with thin targets of halogens or, perhaps, salt is briefly addressed.",
"URL": "http://ui.adsabs.harvard.edu/abs/2009NIMPA.606...83G/abstract",
"title": "Perspective on the role of negative ions and ion\u2013ion plasmas in heavy ion fusion science, magnetic fusion energy, and related fields",
"year_published": 2009,
"fields_of_study": [
"State of matter",
"Physics",
"Ion",
"Electron",
"Beam (structure)",
"Atomic physics",
"Halogen",
"Hydrogen",
"Plasma",
"Free electron model"
],
"first_author": "Larry R. Grisham",
"scholarly_citations_count": 10,
"NER-RE": [
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{
"abstract": "Abstract A thin film of liquid metal is suggested as a grazing incident mirror for robust final optics in a laser inertial fusion energy (IFE) power plant. The amount of laser light the grazing incidence liquid metal mirror (GILMM) can withstand, called the damage limit is limited by the surface disturbances initiated by rapid laser heating. For 0.35-\u03bcm light, the damage limit for a sodium film 85\u00b0 from normal is calculated to be 57 J/cm 2 normal to the beam for a 20 ns pulse and 1.3 J/cm 2 for a 10-ps pulse (2 and 90 m 2 of mirror area per 100 kJ of laser energy at 20 ns and 10 ps, respectively). Feasibility relies on keeping the liquid surface flat to the required accuracy by a combination of polished substrate, adaptive (deformable) optics, surface tension and low Reynolds number, laminar flow in the film. The film's substrate must be polished to \u00b10.015 \u03bcm. Then surface tension keeps the surface smooth over short distances ( 10 mm). Adaptive optics techniques keep the substrate flat to within \u00b10.06 \u03bcm over 100-mm distance and \u00b10.6 \u03bcm over 1000 mm distances, even after 30 years of cumulative damage via neutron irradiation. The mirror can stand the X-ray pulse when located 30 m away from the microexplosions of nominal yield of 400 MJ (50 MJ of X-rays) when Li is used, but for higher atomic number liquids like Na there may be a significant rise in temperature, forcing the use of other X-ray attenuation methods such as attenuation by xenon gas. The GILMM should be applicable to both direct and indirect drive and pulse lengths appropriate to slow compression (\u223c20 ns) or fast ignition (\u223c10 ps). For direct-drive laser beams near the poles (70\u00b0, where 90\u00b0 is vertical), stable thin films become more challenging. Proof of the concept experiments are needed to verify the predicted damage limit and required smoothness.",
"URL": "https://www.sciencedirect.com/science/article/pii/S0920379600002246#!",
"title": "Grazing incidence liquid metal mirrors (GILMM) for radiation hardened final optics for laser inertial fusion energy power plants",
"year_published": 2000,
"fields_of_study": [
"Inertial confinement fusion",
"Optics",
"Adaptive optics",
"Attenuation",
"Thin film",
"Materials science",
"Fusion power",
"Laser",
"Xenon",
"Surface tension"
],
"first_author": "Ralph W. Moir",
"scholarly_citations_count": 6,
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{
"abstract": "The 13th International Workshop on Plasma-Facing Materials and Components (PFMC-13) jointly organized with the 1st International Conference on Fusion Energy Materials Science (FEMaS-1) was held in Rosenheim (Germany) on 9\u201313 May 2011. PFMC-13 is a successor of the International Workshop on Carbon Materials for Fusion Applications series. Between 1985 and 2003 ten 'Carbon Workshops' were organized in Julich, Stockholm and Hohenkammer. Then it was time for a change and redefinition of the scope of the symposium to reflect the new requirements of ITER and the ongoing evolution in the field. Under the new name (PFMC-11), the workshop was first organized in 2006 in Greifswald, Germany and PFMC-12 took place in Julich in 2009. Initially starting in 1985 with about 40 participants as a 1.5 day workshop, the event has continuously grown to about 220 participants at PFMC-12. Due to the joint organization with FEMaS-1, PFMC-13 set a new record with more than 280 participants. The European project Fusion Energy Materials Science, FEMaS, coordinated by the Max-Planck-Institut fur Plasmaphysik (IPP), organizes and stimulates cooperative research activities which involve large-scale research facilities as well as other top-level materials characterization laboratories. Five different fields are addressed: benchmarking experiments for radiation damage modelling, the application of micro-mechanical characterization methods, synchrotron and neutron radiation-based techniques and advanced nanoscopic analysis based on transmission electron microscopy. All these fields need to be exploited further by the fusion materials community for timely materials solutions for a DEMO reactor. In order to integrate these materials research fields, FEMaS acted as a co-organizer for the 2011 workshop and successfully introduced a number of participants from research labs and universities into the PFMC community. Plasma-facing materials experience particularly hostile conditions as they are subjected to extremely high heat loads and very high particle and neutron fluxes. They must have high thermal conductivity for efficient heat transport, high cohesive energy for low erosion by particle bombardment and low atomic number to minimize plasma cooling. These contradictory requirements make the development of plasma-facing materials one of the greatest challenges ever faced by materials scientists. The erosion of plasma-facing materials is one of the main factors influencing the operational schedule of experimental fusion reactors and future power plants. A number of materials selected for current designs cannot withstand the presently foreseen plasma scenarios of a power plant for a commercially viable period of time. Therefore, further coordinated development of plasma scenarios and materials is essential for the realization of fusion as an energy source. The design and development of plasma-facing materials requires a detailed understanding of the processes that occur when a material surface is bombarded with an intense flux of heat, particles and neutrons simultaneously. These materials-related topics are the focus of this series of workshops which has established itself as a discussion forum for experts from research institutions and industry dealing with materials for plasma-facing components in present and future thermonuclear fusion devices. During the joint conference PFMC-13/FEMaS-1 recent developments and research results in the following fields were addressed: carbon, beryllium, and tungsten based materials mixed materials erosion and redeposition high heat flux component development benchmarking of radiation damage modelling synchrotron and neutron based characterization techniques application of advanced transmission electron microscopy and micro-/nano-mechanical testing. With the approaching technical realization of ITER, the ITER-related PFMC topics are naturally the main focus of research. In this respect the start of the ITER-like wall experiment at JET is of paramount importance for our community and several presentations were devoted to this topic. The start of the experimental campaign shortly after PFMC-13/FEMaS-1 will most probably bring about many exciting new results and leaves us eagerly awaiting the next PFMC conference. Several other topics which are of significant relevance for the preparation of ITER were addressed. Among them were dust detection and analysis which is a safety concern and the behaviour of beryllium. Due to the toxicity of beryllium dust, great care has to be taken in the handling of beryllium-containing samples and, as a consequence, only a very limited number of places are available worldwide where such samples can be prepared and investigated. For a solid database and a sound understanding of beryllium and beryllium-containing mixed materials much more effort is necessary in the near future. Naturally, traditional PFMC topics such as first-wall lifetime, testing and characterization of plasma-facing components and hydrogen inventory had their appropriate share of the programme. Not to forget carbon, the nucleating material for this workshop series. Although it will, according to present planning, play only a minor role towards the realization of a DEMO reactor, it is still of importance for current machines and was covered in a large number of poster contributions. Topics receiving continuously increasing attention are those related to devices beyond ITER. Such topics are the development of advanced materials, their behaviour under high heat loads and, in particular, the consequences of neutron damage. The issue which was treated in quite a number of contributions was the simulation of neutron damage by implantation of heavy ions and its influence on hydrogen retention. This is presumably a topic which will receive continuous attention in the years to come. As a consequence of the joint organization with the FEMaS project, several presentations addressed advanced characterization techniques. Remarkable examples of 3D tomography images of plasma-facing components using x-ray- or neutron-based techniques were shown. Such methods allow non-destructive and element-resolved analyses of buried interfaces and are therefore a very promising tool for future investigations of plasma-facing components. It would be desirable that many colleagues of the FEMaS community who attended PFMC-13/FEMaS-1 for the first time would also participate in future events of this series. Thirty five invited lectures and oral contributions and 192 posters were presented by participants coming from research laboratories and industrial companies. Two hundered and eighty two researchers from 27 countries from all over the world participated in the lively and intense exchange of results and new ideas. An additional objective of the series of PFMC workshops was and is to encourage the participation of young talented scientists and to spark their interest in this field. For that reason, the workshop started on its first day with a tutorial session. Experts in their respective fields presented in total eight introductory lectures ranging from the basics of plasma-wall interactions to the engineering of plasma-facing components for ITER. Although originally intended for students and newcomers to the field, these tutorial lectures also enjoy great popularity among senior scientist and are in the meantime an indispensable ingredient and a trademark of this workshop series. The event was organized by the IPP, Garching and received substantial financial support from the European Commission through FEMaS. We are very thankful to the staff of IPP who helped with the organization. Our most cordial thanks and gratitude go to Mrs Christina Stahlberg and Mrs Jutta Koser for their help in the organization and at the front desk. Our most sincere words of appreciation go to our colleague Elmar Neitzert who was in charge of administrative organization. The present proceedings of PFMC-13/FEMaS-1 contain in total 83 peer-reviewed publications covering the contents of most of the oral presentations and of a number of poster contributions which were pre-selected by the programme committee. The papers reflect the development and actual status of the field. We thank all participants for their contributions and we particularly thank the referees for their systematic and diligent reviews of the submitted articles. It is due to their commitment and punctual return of reviews that the proceedings can appear in this relative short time after the meeting. In a meeting of the programme committee during the conferences a few changes in the committee composition were decided. Paul Coad retired and has left the programme committee. We cordially thank Paul Coad for his long-time service as a committee member and wish him the very best for the future. We are very happy that Guy Matthews (CCFE, Culham, UK) accepted the invitation to be his successor. Furthermore, to strengthen the international character of the event, it was decided to invite an additional representative from Japan to the programme committee. Noriyasu Ohno from Nagoya University accepted the invitation. To maintain close contact to the FEMaS community the programme committee further decided to invite Christian Linsmeier from IPP, Garching. Another important decision was taken: in view of the size that the event has reached it was decided to change the name from 'workshop' to 'conference'. So the next event in this series will be the PFMC-14 conference. It will be organized by FZ Julich and most probably take place in spring 2013.",
"URL": "http://iopscience.iop.org/article/10.1088/0031-8949/2011/T145/011001/pdf",
"title": "13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications/1st International Conference on Fusion Energy Materials Science",
"year_published": 2011,
"fields_of_study": [
"Engineering management",
"Physics",
"Nanotechnology",
"Materials science",
"Session (web analytics)",
"Minor (academic)",
"Scope (project management)",
"Energy source",
"Field (computer science)",
"Service (systems architecture)",
"Event (computing)",
"Benchmarking"
],
"first_author": "Wolfgang Jacob",
"scholarly_citations_count": 3,
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"abstract": "A concept has been proposed on the sub-critical nuclear system driven by a fusion neutron source, which can be used to produce fissile nuclear fuel and to transmute long-lived radioactive wastes as a way of early application of the fusion energy technology. The necessity and feasibility to develop that system in China are illustrated based on the prediction of energy source demand in the first half of the 21st century, the current status of nuclear energy supply and the progress in fusion energy technology develepment in the world. A scenario of development steps is also proposed.",
"URL": "http://en.cnki.com.cn/Article_en/CJFDTOTAL-HJSU200008001.htm",
"title": "A fusion neutron source driven sub-critical clear nuclear energy system: A way of early application of fusion energy technology",
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"abstract": "This special issue of Fusion Science and Technology is the first in a series of topical special issues featuring expanded research presented at the 23rd Topical Meeting on the Technology of Fusion ...",
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"abstract": "AbstractIt will be several decades before the first commercial fusion power plant is placed on the electricity grid. However, there are many non-electricity uses for fusion energy that can be realized in the next 5\u201310\u00a0years when the Q value (energy out/energy in) obtained in fusion systems is \u226a1. This paper explores those possibilities dividing them into 3 categories: 1) Commercial Products, 2) Applications for Academia and Utilities, 3) Applications for Military/Governmental uses. At the present time, over 20 near term applications have been identified but it is expected that there could be many more once the fusion community focuses on the near term time frame. Since the near term applications do not require Q\u00a0> 1, all fusion reactions can be considered. This means, for example, that one can consider fusion reactions that not only emit neutrons (from DT and DD) but also other reactions such as D3He that emit high-energy (14\u00a0MeV) protons because they can be used to make short half life Positron Emission ...",
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"abstract": "An international joint project of fusion experimental reactor, the ITER (International Thermonuclear Experimental Reactor), is reviewed in view of long-range fusion energy research and development (R&D). Its purpose, goal, evolution, and the present construction status are briefly reviewed. While the ITER is a core machine in the present stage, generation of electricity is a role of the next-step fusion demonstration power plant \u201cDEMO.\u201d The status of designs and technology R&D for DEMO are also reviewed.",
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"abstract": "A detailed systems analysis code has been used to compare the projected cost of electricity (COE) for inertial fusion energy for direct drive (DD) and indirect drive (ID) target scenarios, based on a diode pumped solid state laser driver with Yb:S-FAP (Yb doped Sr5(PO4)3F) gain media. Previously published target gain curves which resulted in a target gain at the optimal DD operating point that is 30% higher than that for the ID scenario have been used. This gain advantage for DD is offset by a requirement for improved beam smoothing, which was obtained via smoothing by spectral dispersion (SSD) with a 1 THz bandwidth at 349 nm. Such a large SSD bandwidth has a number of effects on laser performance, including greater risk of optics damage from non-linear effects, lowered harmonic conversion efficiency, altered extraction parameters and higher front-end costs. The non-linear effects, which contribute to optical component damage by amplification of intensity non-uniformities, were parameterized through a constraint on the maximum allowable B integral (i.e. the total average phase retardation due to the non-linear indices of all materials traversed by the beam). If we constrain B to be no larger than 1.8 rad, which is the presently accepted safe value based on observations in single shot glass laser facilities, the COEs for DD and ID are predicted to be the same within the uncertainties. If technology permits the B limit to be raised, the optimized COE for DD is predicted to decrease relative to that for ID.",
"URL": "http://ui.adsabs.harvard.edu/abs/2002NucFu..42..354O/abstract",
"title": "Cost of electricity difference for direct and indirect drive targets for inertial fusion energy using a diode pumped solid state laser driver",
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"abstract": "The Energy Independence Conference on Fusion Energy and Plasma Physics was held in Rio de Janeiro (Brazil). This conference was sponsored by the International Union of Pure and Applied Physics (IUPAP). One of the prime purposes of the meeting was to assess and promote the role of developing countries in fusion research. Some one hundred people attended the meeting, with a good representation from the Latin American countries, and participants from Austria, Bangladesh, China, Egypt, India, Israel, Kenya, Malaysia, Poland and Portugal, and with a good selection of specialists from the developed countries.",
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"title": "First Energy Independence Conference: Fusion Energy and Plasma Physics (Report on the Conference, Rio de Janeiro, 17\u201321 August 1987)",
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"abstract": "A method is presented for controlling the trajectory of a vertically injected charged spherical laser fusion target. The position and time of the injected target in fl\u008eight are measured in a position measurement unit using the Arago spot. After the target passes between the fi\u0081rst pair of de\u008eflection plates, where there exists a constant electric \u0081field, the mass-to-charge ratio of the target in fl\u008eight is obtained from the shift in its trajectory. The amplitude of the electric fi\u0081eld applied between the second and third pairs of de\u008eflection plates is calculated using this ratio. After passing through the second and third pairs of defl\u008eection plates, the target defl\u008eects its trajectory to pass through the reactor center. The design parameters of the trajectory control system for a tabletop plasma device and a laser fusion reactor are presented.",
"URL": "https://www.jstage.jst.go.jp/article/pfr/17/0/17_1404088/_pdf",
"title": "In-Situ Mass-to-Charge Ratio Measurement and Trajectory Control of a Vertically Injected Laser Fusion Energy Charged Target via Electric Field",
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"abstract": "The group of 27 papers published in this special issue of Nuclear Fusion aims to monitor the worldwide progress made in the period 2010\u20132012 in the field of thermonuclear fusion. Of these papers, 24 are based on overview reports presented at the 24th Fusion Energy Conference (FEC 2012) and three are summary reports. The conference was hosted by the Government of the United States of America and organized by the IAEA in cooperation with the United States Department of Energy and General Atomics. It took place in San Diego on 8\u201313 October 2012. The overviews presented at the conference have been rewritten and extended for the purpose of this special issue and submitted to the standard double-referee peer-review of Nuclear Fusion . The articles are placed in the following sequence: Overview articles, presented in programme order, are as follows: \u2022 Tokamaks DIII-D research towards resolving key issues for ITER and steady-state tokamaks; Overview of the JET results with the ITER-like wall; Overview of ASDEX Upgrade results; Overview of experimental results and code validation activities at Alcator C-Mod; An overview of KSTAR results; Progress of long pulse and H-mode experiments in EAST; Overview of physics results from the National Spherical Torus Experiment; Overview of physics results from MAST towards ITER/DEMO and the MAST Upgrade; An overview of recent HL-2A experiments; Progress of the JT-60SA project; Overview of recent and current research on the TCV tokamak; An overview of FTU results; New developments, plasma physics regimes and issues for the Ignitor experiment; Recent research work on the J-TEXT tokamak. \u2022 Other MCF Extension of operation regimes and investigation of three-dimensional current-less plasmas in the Large Helical Device; Dynamics of flows and confinement in the TJ-II stellarator; Overview of results from the MST reversed field pinch experiment; Overview of the RFX Fusion Science Program; An overview of intrinsic torque and momentum transport bifurcations in toroidal plasmas. \u2022 ICF The National Ignition Campaign: status and progress; Present status of Fast Ignition Realization EXperiment and inertial fusion energy development. \u2022 Cross device or cross programme topical overviews Energetic particle instabilities in fusion plasmas; Science and technology research & development in support to ITER and the Broader Approach; Multimodal options for materials research to advance the basis for fusion energy in the ITER era. \u2022 Conference summaries of the sessions devoted to: Magnetic confinement experiments on stability, wave\u2013plasma interactions, current drive, heating, energetic particles, plasma\u2013material interactions, divertors, limiters and the scrape-off layer; Magnetic confinement theory and modelling; Inertial confinement fusion. We believe that this issue will be a useful resource for the community and we thank all of the authors and referees for their hard work in preparing the papers for publication.",
"URL": "http://ui.adsabs.harvard.edu/abs/2013NucFu..53j0201T/abstract",
"title": "Special issue: overview and summary reports from the 24th Fusion Energy Conference (San Diego, CA, 8\u201313 October 2012)",
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"abstract": "The economy of scale for multiunit inertial fusion energy (IFE) power plants is explored based on the molten salt HYLIFE-II fusion chamber concept, for the purpose of producing lower cost electricity and hydrogen fuel. The cost of electricity (CoE) is minimized with a new IFE systems code IFEFUEL5 for a matrix of plant cases with one to eight fusion chambers of 250 to 2000-MW (electric) net output each, sharing a common heavy-ion driver and target factory. Improvements to previous HYLIFE-II models include a recirculating induction linac driver optimized as a function of driver energy and rep-rate (average driver power), inclusion of beam switchyard costs, a fusion chamber cost scaling dependence on both thermal power and fusion yield, and a more accurate bypass pump power scaling with chamber rep-rate. A CoE less than 3 cents/kW(electric)-h is found for plant outputs greater than 2 GW(electric), allowing hydrogen fuel production by wafer electrolysis to provide lower fuel cost per mile for higher efficiency hydrogen engines compared with gasoline engines. These multiunit, multi-GW(electric) IFE plants allow staged utility plant deployment, lower optimum chamber rep-rates, less sensitivity to driver and target fabrication costs, and a CoE possibly lower than future fission, fossil, and solar competitors.more\u00a0\u00bb 37 refs., 12 figs., 4 tabs.\u00ab\u00a0less",
"URL": "http://www.osti.gov/scitech/biblio/159672-requirements-low-cost-electricity-hydrogen-fuel-production-from-multiunit-inertial-fusion-energy-plants-shared-driver-target-factory",
"title": "Requirements for low-cost electricity and hydrogen fuel production from multiunit inertial fusion energy plants with a shared driver and target factory",
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"abstract": "With the ITER project now well under way, the countries engaged in fusion research are planning, with renewed intensity, the research and major facilities needed to develop the science and technology for harnessing fusion energy. The Workshop on MFE Roadmapping in the ITER Era was organized to provide a timely forum for an international exchange of technical information and strategic perspectives on how best to tackle the remaining challenges leading to a magnetic fusion DEMO, a nuclear fusion device or devices with a level of physics and technology integration necessary to cover the essential elements of a commercial fusion power plant. Presentations addressed issues under four topics: (1) Perspectives on DEMO and the roadmap to DEMO; (2) Technology; (3) Physics-Technology integration and optimization; and (4) Major facilities on the path to DEMO. Participants identified a set of technical issues of high strategic importance, where the development strategy strongly influences the overall roadmap, and where there are divergent understandings in the world community, namely (1) the assumptions used in fusion design codes, (2) the strategy for fusion materials development, (3) the strategy for blanket development, (4) the strategy for plasma exhaust solution development and (5) the requirements and state of readiness for next-step facility options. It was concluded that there is a need to continue and to focus the international discussion concerning the scientific and technical issues that determine the fusion roadmap, and it was suggested that an international activity be organized under appropriate auspices to foster international cooperation on these issues.",
"URL": "http://pubman.mpdl.mpg.de/pubman/item/escidoc:2145891",
"title": "Summary of the International Workshop on Magnetic Fusion Energy (MFE) Roadmapping in the ITER Era; 7?10 September 2011, Princeton, NJ, USA",
"year_published": 2012,
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"Fusion power",
"World community",
"Technology integration",
"Technical information",
"Magnetic fusion",
"International exchange"
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"first_author": "George H. Neilson",
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"abstract": "The tritium inventory of direct drive inertial fusion energy (IFE) target filling facilities is examined in the interest of minimizing the tritium inventory. A model is described that has been developed to evaluate the tritium inventory of the target filling process as a function of filling and layering parameters, as well as target design parameters. Previous studies by A. Nobile et al. showed that the temperature and the fill system void fraction have a significant effect on the tritium inventory. The current study uses the model to examine the effect of deuterium-tritium (DT) ice layering time and density of the CH foam in the target on the tritium inventory. The study shows that increasing the foam density and decreasing the DT ice layering time significantly reduce the tritium inventory. Fortunately, one-dimensional target design calculations indicate that the foam density in the direct drive target can be increased to {approx}200 mg/cm{sup 3} without significant degradation of the target yield. Having evaluated and minimized the theoretical tritium inventory, calculations were performed with more realistic batch filling scenarios. The inventories associated with 'real' filling scenarios approach the theoretical minimum inventory as the number of batches is increased, resulting in tritium inventories that seemmore\u00a0\u00bb acceptable for future IFE target DT filling facilities.\u00ab\u00a0less",
"URL": "https://www.osti.gov/scitech/biblio/20845886-tritium-inventory-inertial-fusion-energy-target-fabrication-facilities-effect-foam-density-consideration-target-yield-direct-drive-targets",
"title": "Tritium Inventory of Inertial Fusion Energy Target Fabrication Facilities: Effect of Foam Density and Consideration of Target Yield of Direct Drive Targets",
"year_published": 2003,
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"Fusion power",
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"abstract": "A review of structural materials choices under irradiation in fusion environments is presented. Results on the neutron source term and the intensities in the structural materials as a function of pulse time, energy, and protection is given. The role of multiscale modeling for understanding the basic physics in irradiated materials is explained, and simulations of metals under pulse irradiation and SiC are reported.",
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"abstract": "We would like to point out that some contents (includingtexts and one \ufb01gure) of the article \u2018\u2018The Use of PlasmaActuators in Narrowband Active Noise Control\u2019\u2019 by A.Nasiri, published in J. Fusion Energy (2011) 30(5),pp. 394\u2013397 are identical to the article \u2018\u2018Design of anActive Noise Control System using Plasma Actuators\u2019\u2019 byXun Huang, Sammie Chan, Xin Zhang and Steve Gabrielat University of Southampton in 2007. The latter manu-script is denoted by Huang07Ver0 for brevity in the fol-lowing. Huang07Ver0 is actually an abstract of theconference paper (AIAA Paper 2007-3561, denoted byHuang07Ver1 in the following, with the \ufb01nal title of\u2018\u2018Variable Structure Model for Flow-Induced Tonal NoiseControl with Plasma Actuators\u2019\u2019) for 13th AIAA/CEASAeroacoustics Conference (28th AIAA AeroacousticsConference) at Rome, Italy in 2007. The conference paperHuang07Ver1 was further extensively modi\ufb01ed and \ufb01nallypublished in AIAA Journal (2008), 46(1), pp. 241\u2013250. Wewould like to pay attention that Nasiri improperly bor-rowed contents from Huang07Ver0, which can be openlyaccessed at: http://www.coe.pku.edu.cn/tpic/2010823112356675.pdf.These coincidences, for example, are:1. Figures 3 in Nasiri\u2019s article on pp. 395 is a copy ofFigure 1 in Huang07Ver0. The caption is identicalexcept replacing the original symbol of \u2018\u2018__\u2019\u2019 by \u2018\u2018solidline\u2019\u2019 and \u2018\u2018\u2013\u2019\u2019 by \u2018\u2018dotted line\u2019\u2019.2. The text in the third paragraph, right column, onpp. 394 is identical to the \ufb01rst paragraph inHuang07Ver0. They are: \u2018\u2018The plasma actuator is arelatively new and promising technology for \ufb02uid andacoustic control applications due to their simplicityand lack of mechanical moving parts\u2026The secondavenue of research is to develop a closed-loop controlmethod to attenuate \ufb02ow-induced noise actively\u2019\u2019. Thetotal word number of the exactly identical text is 139.Nasiri cited Huang07Ver0 in references [9] as (X.Huang, S. Chan, X. Zhang, S. Gabriel, Design of an ActiveNoise Control System using Plasma Actuators (2006)).However, Huang07Ver0 is an abstract but not a full lengthpaper. The information of the citation is therefore mis-leading. And more importantly, the citation doses not jus-tify the operation of identical copying of the text and \ufb01gurein Huang07Ver0.Last but not the least, the mechanisms of active noisecontrol using plasma in Huang07Ver0 is totally differentfrom the so-called active noise cancellation, which Nasiripresumably applied in his research. The detailed theoreticaldiscussion is beyond the scope of this comment. Interestedreaders can refer to the review paper: Xun Huang and XinZhang, \u2018\u2018Plasma Actuators for Noise Control\u2019\u2019, Interna-tional Journal of Aeroacoustics (2010), 9(4), pp. 679\u2013704.",
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"title": "Comments to the Article \u201cThe Use of Plasma Actuators in Narrowband Active Noise Control\u201d by A. Nasiri Published in J. Fusion Energy (2011) 30, pp. 394\u2013397",
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"abstract": "Physik in unserer ZeitVolume 14, Issue 5 p. 160-160 B\u00fccher The Physical Principles of Thermonuclear Explosive Devices. Von F. Winterberg, Fusion Energy Foundation, 1981 (New York/N.Y. 10019, 888 Seventh Ave), 144 S. $ 9.95. First published: 1983 https://doi.org/10.1002/piuz.19830140511AboutPDF ToolsRequest permissionExport citationAdd to favoritesTrack citation ShareShare Give accessShare full text accessShare full-text accessPlease review our Terms and Conditions of Use and check box below to share full-text version of article.I have read and accept the Wiley Online Library Terms and Conditions of UseShareable LinkUse the link below to share a full-text version of this article with your friends and colleagues. Learn more.Copy URL Share a linkShare onFacebookTwitterLinked InRedditWechat No abstract is available for this article. Volume14, Issue51983Pages 160-160 RelatedInformation",
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