FBR core concepts in the "FaCT" Project in Japan

Oki, Shigeo ; Ogawa, Takashi; Kobayashi, Noboru; Naganuma, Masayuki  ; Kawashima, Katsuyuki; Maruyama, Shuhei   ; Mizuno, Tomoyasu; Tanaka, Toshihiko*

Conceptual design studies of sodium-cooled fast reactor core are performed in Fast Reactor Cycle Technology Development Project (FaCT Project) in Japan. The representative MOX fuel core and the metal fuel core exert excellent performances on safety and reliability, sustainability, economic competitiveness, and nuclear non-proliferation. This paper reviews their feature in terms of reactor physics, and describes recent progress in design studies. In the recent design studies, much interest has been taken in the fuel composition change in the transition stage from light water reactors to fast breeder reactors. The core flexibility is also shown to fulfil the refined objectives such as high breeding and an enhancement of non-proliferation property.