The Use of Thorium in a Nuclear Power System with Thermal and Fast Neutron Reactors

The concept of a fast neutron reactor with a sodium coolant with metallic U–Pu fuel in the core and metallic uranium and thorium in the blankets is considered. The achievement of the required system characteristics for the initial loading and surplus fuel breeding is demonstrated. Several scenarios...

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Bibliographic Details
Published in:Physics of atomic nuclei 2020-12, Vol.83 (8), p.1277-1284
Main Authors: Bobrov, E. A., Andrianova, E. A., Blandinskiy, V. Yu, Teplov, P. S., Gurin, A. V.
Format: Article
Language:English
Subjects:
Electric power systems
Fast neutrons
Fast nuclear reactors
Metal fuels
Nuclear energy
Nuclear fuel cycle
Nuclear fuels
Nuclear reactor components
Nuclear reactors
Particle and Nuclear Physics
Physics
Physics and Astronomy
Reactors
Thermal reactors
Thorium
Uranium
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Summary:The concept of a fast neutron reactor with a sodium coolant with metallic U–Pu fuel in the core and metallic uranium and thorium in the blankets is considered. The achievement of the required system characteristics for the initial loading and surplus fuel breeding is demonstrated. Several scenarios of the development of a two-component nuclear power system in Russia based on the VVER-type thermal reactors and fast reactors with metallic fuel involving the thorium resources are considered.
ISSN:1063-7788
1562-692X
DOI:10.1134/S1063778820080025