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Report No.
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Combined use of MOX and UO$$_2$$ fuel rods in fuel assembly designs for plutonium conservation in FLWR

Uchikawa, Sadao; Nakano, Yoshihiro; Okubo, Tsutomu

The FLWR is an innovative BWR-type reactor with hard neutron spectrum based on the well-experienced LWR technologies. It aims at effective and flexible utilization of uranium and plutonium resources by adopting a two-stage concept of core designs corresponding to the advancement of the fuel cycle technologies and related infrastructures. A new concept of the fuel assembly design named FLWR/MIX has been proposed for the first stage of FLWR to conserve plutonium effectively with a fissile-plutonium conversion ratio of around 1.0, keeping negative void reactivity characteristics. The enriched UO$$_2$$ fuel rods are arranged in the peripheral region of the assembly, surrounding the MOX fuel rods in the central region. Performance evaluation shows that the FLWR/MIX 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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