Simulation of a molten salt fast reactor using the COMSOL Multiphysics software
Author:
Publisher
Springer Science and Business Media LLC
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://link.springer.com/content/pdf/10.1007/s41365-020-00833-3.pdf
Reference18 articles.
1. D. Buckthorp. Introduction to Generation IV nuclear reactors. Structural Materials for Generation IV Nuclear Reactors. Elsevier, Amsterdam. 2017. p. 1–22. https://doi.org/10.1016/B978-0-08-100906-2.00001-X
2. R. Li, S. Wang, A. Rineiski et al., Transient analyses for a molten salt fast reactor with optimized core geometry. Nucl. Eng. Design 292, 164–176 (2015). https://doi.org/10.1016/j.nucengdes.2015.06.011
3. M. Brovchenko, J.-L. Kloosterman, L. Luzzi et al., Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects. EPJ Nucl. Sci. Technol. 5, 2 (2019). https://doi.org/10.1051/epjn/2018052
4. E. Merle-Lucotte, M. Allibert, M. Brovchenko, et al. Introduction to the Physics of Thorium Molten Salt Fast Reactor (MSFR) Concepts. Thorium Energy for the World. Cham: Springer; 2016. p. 223–231. https://doi.org/10.1007/978-3-319-26542-1_34
5. M. Aufiero, A. Cammi, O. Geoffroy et al., Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis. Chem. Eng. Sci. 111, 390–401 (2014). https://doi.org/10.1016/j.ces.2014.03.003
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