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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.
Yuki Edao, Satoshi Fukada, Hidetaka Noguchi, Akio Sagara
Fusion Science and Technology | Volume 55 | Number 2 | February 2009 | Pages 140-151
Technical Paper | doi.org/10.13182/FST09-A4067
Articles are hosted by Taylor and Francis Online.
The rate of tritium released from temperature-controlled Flibe (a mixed molten salt of 2LiF + BeF2) after neutron irradiation was determined comparatively under two different conditions of Ar-H2 (10%) or Ar gas purge at a constant or linearly elevated temperature. Experimental rates of tritium release were analyzed based on its diffusion in Flibe and isotopic exchange between T atoms on surfaces and H atoms included in gaseous components. Gas released from Flibe had compositions of various ratios of HT to TF depending on the different conditions of Ar-H2 or Ar purge gas. The major molecular species of tritium released from Flibe after neutron irradiation was HT under the condition of the Ar-H2 purge and 300°C. The rate of tritium release under the Ar-H2 purge was simulated well by the present analytical model. Although its chemical form immediately after the release was TF under the condition of Ar purge, it was changed to HT partly by interaction with metallic surfaces.