Design Study of Blanket Neutronics of a Commercial Tokamak Fusion-Fission Hybrid Reactor

With the Tokamak driver parameters that could be chieved round about 2000 in the world, neutronics studies and analyses have been performed to the blanket configurtion and materials and self-shielding effect of group cross section for the commercial Tokamak fusion-fission hybrid reactor. The main concern of the study has been the assessment of the global tritium breeding ratio, the global Pu²³⁹ breeding ratio and determinmatton of the total power production. The results show that it's possible to produce 4 tons of Pu²³⁹ per year and net electric output of one GW_e, that the self-shielding effect is not important for the fast fission blanket.