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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
Jeremy A. Burke, X. R. Wang, M. S. Tillack, ARIES Team
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 213-217
Divertor & High Heat Flux Components | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12354
Articles are hosted by Taylor and Francis Online.
The current T-tube divertor design consists of modular helium cooled units. The individual units consist of a steel inner cartridge enclosed in a tungsten alloy outer structure. On top of the outer tube is a layer of pure tungsten armor. Past design and analysis of the T-tube divertor concept has shown that it can accommodate a heat flux up to 10MW/m2. With recent concerns that steady state or transient heat fluxes may be higher than this in the divertor region, the T-tube concept was modified so that it may accommodate higher heat fluxes.