Neutronics design and analysis of water-cooled energy production blanket for a fusion-fission hybrid reactor

Neutronics calculations were performed to analysis the parameters of blanket energy multiplication factor(M) and tritium breeding ratio(TBR) in a fusion-fission hybrid reactor for energy production named FDS-EM(Energy Multiplier) blanket.The most significant and main goal of the water-cooled FDS-EM blanket is to achieve the energy gain of about 1 GW with self-sustaining tritium,which can operate for as long as possible without fuel unloading and reloading.The preliminarily designed neutronics parameters for FDS-EM were presented,which show that the blanket loaded with the Nuclear Waste(transuranic from 33 000 MWD/MTU PWR and depleted uranium) for energy multiplication(M≈90) with tritium self-sufficiency can operate for at least 10 years without fuel unloading and reloading.