A fusion-fission hybrid reactor with pressure tube assemblies is proposed for energy production in this paper. In the light water cooled blanket, spent nuclear fuel from 33 GWD/t LWR and natural uranium oxide are taken as driver fuel for neutron/energy multiplication aiming at increasing uranium utilization efficiency. Tritium self-sufficiency is obtained by Li2O. The home developed NAHR code is employed to simulate the neutronics behavior in the blanket. The plasma conditions and configuration of ITER are used to the neutronics calculations. The results show that the blanket can be operated for at least 5 years with good performance of acceptable energy multiplication and tritium breeding. The first neutron wall loading is lower than 0.57 MW/m2.

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