Investigation of utilizing plutonium as mixed oxide fuel (6); Evaluation of burn-up characteristics of PWR fuels

not registered

Burn-up characteristics of PWR fuels have been investigated for scenario study of FBR introduction and the other studies on practical use of FBR. Nuclear compositions, radioactivity and thermal power of actinides and fission products in the spent fuels of present burn-up (49 GWd/t) and high burn-up (60 GWd/t) have been evaluated using the burn-up calculation code ORIGEN-2. This study was carried out as a part of JNC's feasibility study on commercialized FBR cycle system. Main conditions and results of this study are follows; (1)Evaluation code. :ORIGEN-2 (open code) (2)Fuel enrichment [Burn-up:49 GWd/t, UO fuel(U235 enrichment):4.6 wt%, MOX fuel(Pu enrichment):5.9 Wt%] [Burn-up:60 GWd/t, UO fuel(U235 enrichment):5.3 wt%, MOX fuel(Pu enrichment):7.2 wt%] (3)Evaluation items. Decay change in nuclear compositions, radioactivity and thermal power of actinides and fission products during 10000 years (0, 1, 2, 3, 4, 5, 6, 10, 50,100, 1000, 10000y after burn-up)