Study on FBR core concepts to increase proliferation resistance of plutonium in LWR-FBR transition period

軽水炉から高速増殖炉への移行期におけるプルトニウムの核拡散抵抗性向上のための高速増殖炉炉心概念の研究

Meiliza, Y.; 大木 繁夫 ; 川島 克之; 大久保 努

Meiliza, Y.; Oki, Shigeo; Kawashima, Katsuyuki; Okubo, Tsutomu

The possibility to enhance proliferation resistance of discharged plutonium in fast breeder reactor (FBR) has been investigated in terms of reactor core design aspects. The provisional target for proliferation resistance measures based on Saito's ATTR is defined. It is found that a few percent of plutonium loading and/or Am/Cm loading, which come from various types of spent fuel, might satisfy the provisional target with a minimum impact on the core neutronic performances. On Am/Cm loading core, decay heat constraints for fuel handling aspects are found to be important and should be considered in design. There is not significant change on the current developing scenarios for LWR-FBR transition period by applying the measures based on Saito's ATTR. It is found that applying Kimura's proposal, 15% Pu content requires about 7% MA loading fraction both in the core and the blanket, and it only can be applied at limited case. The period to consume minor actinides is shorter than to consume plutonium.