STUDY OF A THERMONUCLEAR REACTOR BLANKET WITH FISSILE NUCLIDES.
Technical rept. (Master's thesis),
MASSACHUSETTS INST OF TECH CAMBRIDGE RESEARCH LAB OF ELECTRONICS
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The use of fissile nuclides in a fusion power reactor heat-extraction blanket is investigated from the point of view of tritium regeneration and power production. The existence of a stable, steady-state D-T plasma in a cylindrical configuration is postulated. Nuclear reaction rates are analyzed with the aid of theoretical methods and multigroup, multiregion computer codes developed by A. J. Impink, Jr. Codes developed by W. G. Homeyer were used to calculate nuclear heating rates. Optimization studies of several blanket configurations show that a blanket with a thin Mo first wall, a narrow, fused LiF2BeF2 first-wall coolant region, and about 50 cm 21 C and 79 fused LiF-BeF2-UF4 primary attenuator region with 17 to 27 mole per cent U238F4 and about 50 Li6 enrichment is feasible and practical. The calculated tritium regeneration is adequate. The total heat recovery is approximately twice that in a nonfissile blanket approximately 90 of the heat is liberated in the primary attenuator region. The heating rate in the first wall and in the coolant region is independent of the UF4 salt composition. The thermonuclear power limit is about 5 Mwsq. m of neutron energy incident on the first wall. The performance of blankets with a UF4 fusedsalt coolant region was found to be marginal fissioning metallic first-wall configurations are not feasible. Author