Design and Analysis of Solid Blanket Concept for Hybrid Fusion-Fission Facility

The article discusses the results of conceptual design and analysis for solid blanket of a hybrid fusion-fission facility based on a tokamak-type fusion reactor with magnetic plasma confinement. This blanket is intended to breed a nuclear fuel for the RF atomic industry by transmutation of the initial isotopes 238 U and 232 Th into the target 239 Pu and 233 U, respectively. Various design options of the solid blanket of the hybrid reactor facility (HRF) and its core, technological schemes of blanket mounting/dismounting and maintenance, choice of raw material compositions, coolants, and structural materials, and results of preliminary neutron analysis for the solid blanket are presented.