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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.
W. Beyrich, G. Spannagel
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 337-342
Technical Paper | Analysis | doi.org/10.13182/NT79-A32190
Articles are hosted by Taylor and Francis Online.
If different laboratories using thermionic mass spectrometry determine in routine operation a 235U concentration of ≈0.7% in the same sample material, their measurement results deviate by at least 0.8% (relative) in ≈50% of the cases. The application of gas mass spectrometry reduces this deviation to 0.1 or 0.05%, the more favorable value being obtained by measurements in which the same reference material is used by all laboratories. These results were obtained by application of an empirical evaluation procedure that, contrary to the usual statistical tools, is not restricted to homogeneous data material. The data were taken from two interlaboratory evaluation programs performed recently on the isotopic abundance determination of 235U in uranium hexafluoride by mass spectrometry.