Neutronic analysis of Z-pinch driven fusion-fission hybrid reactor blanket

As a competitive energy system, Z-pinch driven fusion-fission hybrid reactor (Z-FFR) is developed in concept study stage, while blanket research is one important part. In this paper the Z-FFR blanket design model is set up, and influence factor, neutron balance, flux, power density and burnup of the model are analyzed. The average energy multiplication factor (M), tritium breeding ratio (TBR) and fuel breeding ratio (F/B) for 50 years are 14.91, 1.294 and 5.140, respectively, which can meet the design requirements. Considering pulse characteristic of fusion source, the transient neutronics properties are also studied. In fuel zone neutron, there are three parts of pulse: fusion neutron pulse, prompt fission neutron pulse and delayed fission neutron pulse. Most of the energy in fuel zone is deposited in 0.01 s. The complete neutron parameters of Z-FFR blanket are given, which provide the foundation for the concept study.