The data enclosed in this repository is associated with the manuscript for an article submitted to the European Physical Journal - Nuclear mid February 2019 and Nuclear Engineering and Design end of March 2019. 
The articles are adaptation of an articles presented at the ICONE26 Conference in London, July 2018, the CFD4NRS-7 Workshop in Shanghai, September 2018 and the NUTHOS-12 topical meeting in Qingdao, October 2018.

References:

G.M. Cartland-Glover, S. Rolfo, A. Skillen, D.R. Emerson, C. Moulinec, D. Litskevich, B. Merk. "Modelling the neutronics of a molten salt fast reactor using DYN3D-MG for the investigation of the application of frozen wall technology". In proceedings of the 26th International Conference on Nuclear Engineering -- ICONE 26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues
London, England, July 22–26, 2018. doi:10.1115/ICONE26-82170, paper V005T05A024.

G.M. Cartland-Glover, A. Skillen, D. Litskevich, S. Rolfo, D.R. Emerson, B. Merk, C. Moulinec. "On the numerical modelling of frozen walls in a molten salt fast reactor". In proceedings of the OECD/NEA&IAEA CFD4NRS-7 Workshop, Application of CFD/CMFD Codes to Nuclear Reactor Safety and Design and their Experimental Validation, Shanghai, September 4-6, 2018.

G.M. Cartland-Glover, A. Skillen, S. Rolfo, D.R. Emerson, C. Moulinec, D. Litskevich, B. Merk. "On the feasibility of the application of frozen walls to a molten salt fast reactor". In proceedings of the 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety -- NUTHOS-12, Qingdao, China, October 14-18, 2018.

----------------
The data is in the form of neutron cross sections which have been formatted for the DYN3D-MG code.

The subdirectory coreregion contains the reactor core neutron cross sections for the fuel salt eutectic LiF-PuF3-UF4 over the temperature range 623.15 K - 1198.15 K.  Below  814.22 K the fuel salt eutectic is assumed solid. Details of the assumed physical properties of the fuel-salt eutectic are given in the above references. The cross-sections were used in the coupled neutronic and computational fluid dynamic simulation of a cylindrical reactor with a low resolution.

The subdirectory coreandreflector contains the reactorcore, wall and reflector neutron cross sections for the fuel salt eutectic LiF-PuF3-UF4 over the temperature range 623.15 K - 1198.15 K.  Below  814.22 K the fuel salt eutectic is assumed solid. Details of the assumed physical properties of the fuel-salt eutectic are given in the above references. The cross-sections were used in the coupled neutronic and computational fluid dynamic simulation of a reactor with the EVOL-optimized configuration.

----------------
The raw data was prepared using the SCARF (scarf.rl.ac.uk). The data was generated using SERPENT (http://montecarlo.vtt.fi/). SERPENT (version 2.1.29) modelled the neutronic behaviour of the molten salt fast reactor using the Monte Carlo method. The data was reformatted to a format that the nodal neutron diffusion solver DYN3D-MG (https://www.hzdr.de/db/Cms?pOid=11771&pNid=542) could read.  This is the format in which neutron cross-sections are given.

----------------
The project was funded by the following grants:

 - EPSRC through the Feasibility Study in Energy Research scheme (Ref: EP/R001618/1)

Additional support was obtained from the following grants:

 - EPSRC EP/N016602/1 and EP/N033841/1
 - Future Emerging Technologies funding scheme of the European Union’s Horizon 2020 research and innovation programme under grant agreement No 671564
 - EPSRC RAP-Tier 2 allocation provided access to the CIRRUS cluster

