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Breeder-type operation based on the LWR-MOX fuel technologies in light water reactors with hard neutron spectrum (FLWR)

軽水冷却高速炉FLWRにおけるプルサーマル燃料技術に立脚した増殖型運転の実現

内川 貞夫; 大久保 努; 中野 佳洋

Uchikawa, Sadao; Okubo, Tsutomu; Nakano, Yoshihiro

軽水冷却高速炉(FLWR)においてプルサーマル燃料技術に立脚して増殖型運転を実現する燃料集合体概念として、MOX燃料棒とUO$$_{2}$$燃料棒を非均質に配置した新たな設計概念を構築し、使用するMOX燃料ペレットのプルトニウム最大富化度をプルサーマル用燃料加工施設での取扱可能範囲としながら、核分裂プルトニウム残存比1.0以上を実現できる見通しを得た。

An advanced LWR concept, FLWR, is a BWR type reactor, in which the moderation of neutron in the core is reduced by use of tight-lattice fuel rod configuration. It aims at realizing effective and flexible utilization of uranium and plutonium resources by two stages, corresponding to the advancement of the fuel cycle technologies and related infrastructure. The present paper has proposed advanced fuel and core designs for realization of breeder-type operation in the first stage of FLWR. To achieve a high fissile-plutonium conversion ratio over 1.0, a new design concept of the MOX fuel assembly has been developed, in which MOX rods are arranged in the central region of the assembly, while enriched UO$$_{2}$$ rods in the peripheral region of the assembly. Performance evaluation shows that the proposed concept is feasible and promising under the framework of the UO$$_{2}$$ and MOX fuel technologies and related infrastructures, which have been established for the current LWR-MOX utilization.

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