Preliminary analyses of neutronics schemes for three kinds waste transmutation blankets of fusion-fission hybrid

The neutronics schemes of the helium-cooled waste transmutation blanket, sodium-cooled waste transmutation blanket and FLiBe-cooled waste transmutation blanket were preliminarily calculated and analysed by using the spheroidal tokamak (ST) plasma configuration. The neutronics properties of these blankets' were compared and analyzed. The results show that for the transmutation of ²³⁷Np, FLiBe-cooled waste transmutation blanket has the most superior transmutation performance. The calculation results of the helium-cooled waste transmutation blanket show that this transmutation blanket can run on a steady effective multiplication factor (k_eff), steady power (P), and steady tritium production rate (TBR) state for a long operating time (9.62 years) by change ²³⁷Np's initial loading rate of the minor actinides (MA). (authors)