Molten salt reactors are a very promising option for the development of highly innovative solutions for the nuclear energy production of the future. New results of the application of the nodal diffusion code, DYN3D-MG, to model the steady state operation of molten salt fast reactors based on circulating fluoride salt, are presented here. The cross-section set was prepared using the Monte Carlo particle transport code, SERPENT. Full core comparisons between SERPENT and DYN3D-MG demonstrate that the molten salt fast reactor steady state operation can be modelled by DYN3D-MG within the required accuracy. The work is an important initial step for the development of a coupled CFD/neutron physics code system. This code system will finally be applied for the investigation of an innovative material protection scheme to avoid the contact of the liquid salt with the structural material.
- Nuclear Engineering Division
Modelling the Neutronics of a Molten Salt Fast Reactor Using DYN3D-MG for the Investigation of the Application of Frozen Wall Technology
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Cartland-Glover, GM, Rolfo, S, Skillen, A, Emerson, DR, Moulinec, C, Litskevich, D, & Merk, B. "Modelling the Neutronics of a Molten Salt Fast Reactor Using DYN3D-MG for the Investigation of the Application of Frozen Wall Technology." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues. London, England. July 22–26, 2018. V005T05A024. ASME. https://doi.org/10.1115/ICONE26-82170
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