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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.
John R. Wiley
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 268-272
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16317
Articles are hosted by Taylor and Francis Online.
Borosilicate glasses containing actual high-level Savannah River Plant waste were leached in static, distilled water. Leach rates based on 90Sr, 137Cs, and plutonium analyses were similar: 10−5 to 10−6 g of glass/(cm2·day) initially, 10−7 to 10−8 g/(cm2·day) after two weeks, and 10−8 to 10−9 g/(cm2·day) after 100 days. The leach rates were not directly correlated with waste composition, but were qualitatively related to the tendency of the glass to devitrify that could be caused by certain combinations of waste components. According to a proposed model, leach rates were diffusion-controlled during the entire 100-day test.