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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.
H. T. Bach, T. H. Allen, D. D. Hill, P. T. Martinez, R. B. Schwarz, S. N. Paglieri, J. R. Wermer
Fusion Science and Technology | Volume 54 | Number 1 | July 2008 | Pages 197-201
Technical Paper | Tritium Measurement | doi.org/10.13182/FST08-A1795
Articles are hosted by Taylor and Francis Online.
Before surplus plutonium pits can be decommissioned and converted into metal oxides to be used as reactor fuels, residual tritium must be reduced to an acceptable level. We have developed two analytical methods involving melting and acid dissolution, combined with liquid scintillation counting as a quantitative and sensitive technique for measuring residual tritium in Pu metal. The detection limit, linearity, and reproducibility of these analytical methods must be validated with a series of metal tritide standards. Since there are no commercially available metal tritide standards, we have developed a technique for their synthesis. The synthesis of these low-level metal tritide standards is accomplished by charging cerium powder with a known amount of tritium to form a master cerium tritide alloy and then by aliquoting from this master alloy and diluting with pure cerium powder to form a series of standards with different tritium concentrations. The major difficulty in synthesizing these standards is that the samples contain extremely low levels of tritium, which span over three decades of concentrations. The synthesis technique and initial data obtained for cerium hydride samples will be presented.