Development of long-lived radioactive nuclides transmutation technology with metallic fuel FBR

Transmutation rates of Transuranium (TRU) isotopes for mox fuel 1,000 MWs FBR that was designed as demonstration FBR and for metallic fuel FBR that has the same core configuration in the case of mox fuel core are discussed. Amounts of TRU isotopes contained in core are 5, 10 and 15 % of amounts of U, Pu fuels. The burnup calculations are performed with SLAROM code and CITATION-TRU code improved CRIEPI on burnup calculation method. The results are: a) TRU isotopes raise keff reactivity in end of cycle. b) The transmutation rates of TRU isotopes with metallic fuel are higher than with mox fuel. c) Amounts of Pu needed burnup are decreased with increase of amounts of TRU isotopes. (author)