Neutronics analysis of blankets for a hybrid fusion neutron source

Modern challenges of nuclear power concern a potential shortage of nuclear fuel for fission reactors in the case of intensive development of the nuclear industry, insufficient development of economic and safe fast reactors, underutilization of the closed fuel cycle, spent nuclear fuel reprocessing, nuclear power safety and nonproliferation of weapon-grade materials. Expected progress in solving these problems is associated with the development of a hybrid fusion neutron source (FNS) with a subcritical blanket, using the closed nuclear fuel cycle. In this work the capability of hybrid fusion neutron source blankets in the generation of 233U, 239Pu and 3H nuclides, reprocessing of spent nuclear fuel, electricity and heat production are investigated. The basic kinds of blankets are considered. There is a uranium and thorium solid-state blanket, a blanket with the use of heavy water solutions of salts, oxides of uranium and thorium, a molten lead and a molten salt blanket. The structure and geometrical parameters of the blankets, the moderators, and the fertile materials are optimized to obtain the ultimate nuclear fuel yield at the minimal accumulation of radiation toxic wastes. The neutronics comparative analysis of the different blanket models is presented. In the results, the optimal FNS blanket models have been chosen.