[2D05-08] Molten Chloride Salt Reactor

11:15 AM - 11:30 AM JST(2:15 AM - 2:30 AM UTC)

[2D07] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (V)(3) Burnup characteristics of a chloride molten salt fast reactor using fuel with Pu enrichment below the domestic upper limit

*Koshi Mitachi¹, Yoichiro Shimazu¹ (1. BERD)

Keywords:

molten salt reactor,fast reactor,chloride salt,Trans Uranium Elements,Pu enrichment

When plutonium fuel is used in Japan, the Japan-US Nuclear Cooperation Agreement limits plutonium enrichment (=plutonium/heavy metals) to 0.5 or less. In this study, we analyzed burnup characteristics of a conversion type chloride molten salt fast reactor using fuel with Pu enrichment of 0.47, and confirmed that the results showed small difference from the previous results using fuel with Pu enrichment of 0.89.