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

• Published in: Physics of atomic nuclei Vol. 86; no. Suppl 2; pp. S112 - S121
• Main Authors: Strebkov, Yu. S., Afremov, D. A., Arhipov, O. P., Vershinin, I. V., Danilov, I. V., Ivanov, V. O., Kozlov, S. A., Korostelev, A. B., Larionov, I. A., Leshukov, A. Yu, Loginov, D. Yu, Lopatkin, A. V., Lukasevich, I. B., Mezhina, E. R., Poddubnyi, I. I., Pulinets, A. A., Razmerov, A. V., Sviridenko, M. N., Sysoev, A. G., Cherepnin, Yu. S.
• Format: Journal Article
• Language: English
• Published: Moscow Pleiades Publishing 01-12-2023
• Subjects: Particle and Nuclear Physics; Physics; Physics and Astronomy; nuclear fuel breeding; solid blanket; hybrid reactor facility
• ISSN: 1063-7788; 1562-692X
• DOI: 10.1134/S1063778823140132

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.