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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.
O. K. Tallent, J. C. Mailen
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 416-419
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31806
Articles are hosted by Taylor and Francis Online.
The effects of Cu2+, Hg2+, Zn2+, La3+, Ce3+, Al3+, Pu4+, Th4+, and Zr4+ metal ion impurities on PuO2 dissolution in 8.0M HNO3—0.1M HF solution at 100°C have been investigated. Results based on 1.0 h of dissolution time show that such metal ions as Al3+, Pu4+, Th4+, and Zr4+, which form strong fluoride complexes, greatly decrease the dissolution rate, whereas such metal ions as Cu2+, Hg2+, Zn2+, La3+, and Ce3+, which form relatively weak fluoride complexes, have little or no effect. Fluoride ion activities in the dissolvents were calculated based on an empirical equation, K1aF + aF − 0.10 γs = 0, where K1, aF, and γs denote first metal ion fluoride complex stability constant, fluoride ion activity, and stoichiometric fluoride ion activity coefficient, respectively. The PuO2 dissolution rates were found to increase linearly with increase in the calculated fluoride ion activities.