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- W49224808 abstract "In recent work, the regeneration of CANDU spent fuel in a deuterium-tritium (D-T)-driven hybrid reactor blanket has been investigated. Scientists and engineers now have begun to believe that the economic feasibility of advanced fusion fuel cycles will be possible soon after the first generation of reactors based on conventional fusion fuel (D-T). In the work reported in this paper, a semicatalyzed deuterium-deuterium (D-D) fusion reactor has been investigated to drive a fissile blanket that contains CANDU spent fuel. The fuel regeneration has been studied coupled with substantial electricity production in situ. The main conclusions can be summarized as follows: (1) The spent-fuel regeneration in a semicatalyzed (D-D) fusion-fission blanket proceeds faster than the pure (D-T)-driven hybrid blanket per incident fusion neutron energy load at the first wall; (2) The high blanket multiplication factor M allows one to produce abundant electricity in situ; (3) The blanket produces a substantial amount of tritium for satellite (D-T) fusion reactors; (4) The spent fuel can be regenerated to be used in an advanced CANDU reactor with thorium recycling, even to the degree necessary for use in a conventional LWR. 1 ref., 1 fig." @default.
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- W49224808 date "1989-01-01" @default.
- W49224808 modified "2023-10-18" @default.
- W49224808 title "Heavy water reactor spent-fuel regeneration with fusion neutrons" @default.
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