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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.
M. B. Rozenkevich, I. L. Rastunova, S. V. Prokunin
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 466-469
Technical Paper | Water Processing | doi.org/10.13182/FST08-A1855
Articles are hosted by Taylor and Francis Online.
Detritiation of light water wastes down to a level permissible to discharge into the environment while simultaneously concentrating tritium to decrease amount of waste being buried is a constant problem. The laboratory setup for the light water detritiation process is presented. The separation column consists of 10 horizontally arranged perfluorosulphonic acid Nafiontype membrane contact devises and platinum catalyst (RCTU-3SM). Each contact device has 42.3 cm2 of the membrane and 10 cm3 of the catalyst. The column is washed by tritium free light water (LH2O) and the tritiumcontaining flow (FHTO) feeds the electrolyser at = GH2/LH2O = 2. A separation factor of 66 is noted with the device at 336 K and 0.145 MPa.