Abstract
A subcritical molten salt reactor with an external neutron source is studied computationally as a facility for incineration and transmutation of minor actinides from spent nuclear fuel of reactors of VVER-1000 type and for producing 233U from 232Th. The reactor configuration is chosen, the requirements to be imposed on the external neutron source are formulated, and the equilibrium isotopic composition of heavy nuclides and the key parameters of the fuel cycle are calculated.
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NJOY99.0 Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data, RSICC Peripheral Shielding Routine Collection, Documentation for PSR-480/NJOY99.0 Code Package (Oak Ridge National Laboratory, 2000).
Special Issue on Evaluated Nuclear Data File ENDF/B-VII.0, Nuclear Data Sheets 107 (12) (2006).
Los Alamos National Laboratory Report LA-UR-031987 (Los Alamos National Laboratory, 2003).
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Original Russian Text © V.A. Nevinitsa, A.A. Dudnikov, V.Yu. Blandinskiy, A.L. Balanin, P.N. Alekseev, Yu.E. Titarenko, V.F. Batyaev, K.V. Pavlov, A.Yu. Titarenko, 2014, published in Voprosy Atomnoi Nauki i Tekhniki. Seriya: Fizika Yadernykh Reaktorov, 2014, Nos. 1-2, pp. 44–50.
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Nevinitsa, V.A., Dudnikov, A.A., Blandinskiy, V.Y. et al. The procedure and results of calculations of the equilibrium isotopic composition of a demonstration subcritical molten salt reactor. Phys. Atom. Nuclei 78, 1246–1251 (2015). https://doi.org/10.1134/S1063778815110137
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DOI: https://doi.org/10.1134/S1063778815110137