A sodium-cooled MOX-fueled FBR core concept to improve nuclear proliferation resistance was proposed. First, we set an index for the nuclear proliferation resistance. In a previous study, reactor-grade Pu was defined such that the Pu-240 isotopic ratio was larger than 18%. Another study defined nuclear proliferation resistance with the Pu-238 isotopic ratio considering its higher spontaneous fission rate and decay heat. We tentatively use the total isotope composition ratio of Pu-238 and Pu-240 as a proliferation resistance index in line with the earlier studies. Next, we designed the sodium-cooled mixed-oxide (MOX)-fueled core concept with the breeding ratio (BR) of over 1.1 without a radial blanket. To attain the index for nuclear proliferation resistance, we added minor actinides (MAs) to the axial blanket fuel (AB). Contents of MAs in the AB to achieve the proliferation resistance index were evaluated. For the case of Np as a representative MA, the minimum content of Np to achieve the index was 3%. And, for the case of loading all MAs, the minimum content of MAs was 10.5%.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4934-7
PROCEEDINGS PAPER
Fast Breeder Reactor Core Concept to Improve Nuclear Proliferation Resistance
Koji Fujimura,
Koji Fujimura
Hitachi, Ltd., Hitachi, Ibaraki, Japan
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Satoshi Itooka,
Satoshi Itooka
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
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Takeshi Nitawaki
Takeshi Nitawaki
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
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Koji Fujimura
Hitachi, Ltd., Hitachi, Ibaraki, Japan
Satoshi Itooka
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
Takeshi Nitawaki
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
Paper No:
ICONE18-29214, pp. 13-17; 5 pages
Published Online:
April 8, 2011
Citation
Fujimura, K, Itooka, S, & Nitawaki, T. "Fast Breeder Reactor Core Concept to Improve Nuclear Proliferation Resistance." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 6. Xi’an, China. May 17–21, 2010. pp. 13-17. ASME. https://doi.org/10.1115/ICONE18-29214
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