Potential of a fusion-fission hybrid reactor using uranium for various coolants to breed fissile fuel for LWRs

摘要

In this study, neutronic performances of the (D,T), driven hybrid blandkets, fuelled with UC_2 and UF_4, are invetigated under first wall load of 5 MW/m~2. The fissile fuel zone is considered to be Cooled with three coolants: gas (He or CO_2), flibe (Li_2BeF_4), and natural lithium. The behaviour of The UC_2 and UF_4 fuels are observed during 48 months for discrete time intervals of △t=15 days And by a plant factor of 75 /100. At the end of the operation time, calculations have shown that Cumulative Fissile Fuel Enrichmetn (CFFE) values varied between 5 and 8.5 /100 depending on the Fuel and coolant type.