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

descriptionPublicationkeyboard_double_arrow_right Report , Other literature type 27 Feb 1959 United States Publisher:Office of Scientific and Technical Information (OSTI)

Authors: Guthrie, C. E.;

doi: 10.2172/4098567

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

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Abstract

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)

Country

United States

Related Organizations

University of North Texas System
United States
Oak Ridge National Laboratory
United States

Keywords

Reactor Technology, 330, Economics, Thorium, Fused Salt Fuel, Fuels, Reactors, Uranium 233, Uranium 235, Recovery, Fission Products, Waste Processing, Graphite Moderator

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