Preliminary Neutronics Calculation of Thorium-Based and MA Transmutation Breeding Blanket for Hybrid Fusion-Fission Reactor

Hybrid fusion-fission reactor has advantages of production of nuclear fuel and transmutation of long-life nuclear waste and having inherent safety,at the same time,demand is significantly reduced compare to the pure fusion reactor.Breeding blanket is the key part of the fusion-fission reactor and in the past,the uranium-plutonium blanket concept was widely investigated.Considering the problem of uranium-plutonium cycle and abundant in thorium in our country,in this work,a thorium-based breeding and MA(minor actinides) transmutation blanket concept was proposed and the preliminary neutronics calculation was discussed.One-dimensional transport and burnup calculation code BISONC and Monte-Carlo transport code MCNP were used to calculate the key parameters,such as tritium breeding ratio,production of 233U mass and power density,and so on.The fuel of 233U enrichment can be 3.65%.It is the foundation for optimization of the blanket.