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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.
Takeshi Muranaka, Nagayoshi Shima
Fusion Science and Technology | Volume 54 | Number 1 | July 2008 | Pages 297-300
Technical Paper | Environment and Safety | doi.org/10.13182/FST08-A1817
Articles are hosted by Taylor and Francis Online.
An electrolytic cell, essentially composed of a solid polymer electrolyte (SPE) film and porous dimensionally stable electrodes (DSEs), was designed to reduce the electrolytic voltage in an electrolyzer. The device achieved a tritium recovery factor of 0.836±0.021 for a volume reduction factor of five when operated at a current of 6 A, while maintaining a water bath temperature below 2 °C. Sample and standard waters were simultaneously enriched by connecting two electrolytic cells in series. The sample water was first enriched using a commercially available apparatus with a large electrolytic current of 50 A until the volume in the sample water was reduced to approximately one fifth of the original volume. This "two-stage electrolysis" enrichment was applied to coastal seawaters from the Aomori prefecture. Tritium concentrations, ranging from 0.2 to 0.5 Bq/L, were found, with a measurement error (i.e. a statistical error of one sigma) of ca. 10% of the obtained values.