Neutron-Physical Aspects of the Conceptual Validation of a Fast Reactor with an Open Fuel Cycle

This article is devoted to the pressing issue of achieving fuel security by realizing in fast reactors the best breeding of new fissile materials from the initial isotopes and using the accumulated fissile isotopes in the same reactor irrespective of the rates at which the spent nuclear fuel is repr...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2015-02, Vol.117 (4), p.223-230
Main Authors: Kodochigov, N. G., Sorokin, S. E., Sukharev, Yu. P.
Format: Article
Language:English
Subjects:
Analysis
Approximation
Energy
Energy resources
Fission
Fuel cycles
Fuels
Hadrons
Heavy Ions
Isotopes
Nuclear Chemistry
Nuclear Energy
Nuclear engineering
Nuclear fission
Nuclear fuels
Nuclear industry
Nuclear Physics
Nuclear power generation
Nuclear reactor components
Nuclear reactors
Physics
Physics and Astronomy
Reactor fuel reprocessing
Reactors
Studies
Uranium
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Summary:This article is devoted to the pressing issue of achieving fuel security by realizing in fast reactors the best breeding of new fissile materials from the initial isotopes and using the accumulated fissile isotopes in the same reactor irrespective of the rates at which the spent nuclear fuel is reprocessed in the external fuel cycle. Two fast-reactor concepts based on the same principle are validated by computational means. In the first one, the fissile isotope is replenished with the breeding isotope by moving the neutron flux or energy release along the initially formed composition, consisting of a seed zone and a breeding zone (traveling wave of fission concept); in the second one, the motion of the neutron flux is replaced by the movement of the fuel composition, comprised of fissile and breeding materials (standing wave of fission concept).
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-015-9914-8