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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.
Hidetoshi Hashizume, Noritaka Yusa, Kentaro Matsui
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 523-527
Blanket Design and Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12435
Articles are hosted by Taylor and Francis Online.
The present study clarifies feasibility of a new concept for the Flibe blanket system with Cesium from the thermonuclear viewpoint. Through this study it was revealed at first that the melting temperature of Flibe can be lowered with adding the CsF. And then the tritium breeding ratio when 137Cs was mixed in the Flibe was evaluated by using the neutron transport calculation code of MVP. The numerical results indicate that the TBR decreases gradually by adding Cs substituted for Beryllium.
