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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.
Edward J. Bouwer, John W. McKlveen, W. J. McDowell
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 102-111
Technical Paper | Analysis | doi.org/10.13182/NT79-A32166
Articles are hosted by Taylor and Francis Online.
A method utilizing solvent extraction coupled with liquid scintillation spectrometry has been developed for the assay of uranium and thorium in fertilizers and phosphate-containing minerals and chemicals. Trioctylphosphine oxide in toluene is used to extract uranium and thorium from a perchloric and nitric acid solution, with phosphate interference being suppressed by the addition of aluminum ion. The uranium and thorium are stripped from this solution, and uranium is separated from the thorium by selective reextraction of uranium into a scintillator with Adogen 364 (tertiary amine) sulfate. The thorium remaining in the aqueous is reextracted into another scintillator with (primary) 1-nonyldecylamine sulfate. Both nuclides are counted separately in a high-resolution liquid scintillation spectrometer. The sensitivity of the counting method is enhanced by the use of pulse-shape rejection of the beta-gamma background. Results indicate a detection threshold of 0.0038 pCi of uranium (1.1 part/108) with a 1000-min counting time. Reproducibility of ±2.5% was found at the 50-ppm level. For thorium detection, thresholds are 4 part/1013 for the same counting time with ±3.0% average recovery of 230Th and 7 part/108 of 232Th.