A solid blanket concept for a fusion-fission hybrid reactor plant producing nuclear fuel

Abstract

As part of a project for a solid blanket of a fusion-fission hybrid plant for neutron irradiation of ²³⁸U and ²³²Th isotopes with their transmutation into ²³⁹Pu and ²³³U consumed by nuclear power industry, studies were conducted to select the optimal source material composition, coolant, and structural materials. Several design options for the blanket module were analyzed and compared; the most promising directions for further development of the blanket design were formulated. The obtained ²³⁹Pu and ²³³U productivity for the developed designs of uranium and thorium blanket modules was used to assess the fusion plant power, which is necessary to achieve an integral productivity comparable to the consumption of the VVER-1000 fuel isotope.