Neutronics analysis of the dual-cooled waste transmutation blanket for the FDS

Abstract A preliminary conceptual design of dual-cooled long-lived radioactive waste transmutation blanket for the Fusion-Driven sub-critical hybrid System (FDS) is presented on the basis of feasible plasma physics and technology level i.e. the neutron wall loading is assumed to 0.5 MW/m 2 with availability of 50%. The concept has the attractive advantages e.g. tritium is self-sustainable, plutonium for the purpose of neutron multiplication is self-sustainable and the thermal power output is stable. The one-dimensional neutronic transport calculation using the discrete ordinate method and burnup calculation using the direct numerical method are carried out to assess the performance of the blanket.