FUEL CYCLE COSTS IN A GRAPHITE MODERATED U$sup 235$-Th FUELED FUSED SALT REACTOR | Zendy

Caitlyn Guthrie | Zendy

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FUEL CYCLE COSTS IN A GRAPHITE MODERATED U$sup 235$-Th FUELED FUSED SALT REACTOR

Author(s) -

Caitlyn Guthrie

Publication year - 1959

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/4098567

Subject(s) - fuel cycle , nuclear engineering , graphite , waste management , fission , uranium 233 , liquid fluoride thorium reactor , environmental science , radiochemistry , materials science , nuclear physics , chemistry , nuclear reactor core , engineering , physics , mox fuel , neutron , plutonium , metallurgy

A fuel-cycle economic study was made for a 315-Mw(e) graphite-moderated U/sup 235/-Th-fueled fused-salt reactor. Fuel cycle costs of approximately 1.3 mills/kwh may be possible for such reactors when reprocessed for U/sup 233/ and U/ sup 235/ recover y at the end of a 9-year cycle. Continuous removal of fission products during the reactor cycle does not appear to offer any great economic advantage for the converter reactor considered. (auth

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