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• W2031640062 abstract "Recovering of minor actinides from spent nuclear fuel is investigated for heterogeneous recycling in Generation-IV reactors. After plutonium, americium is the main contributor to residual heat of long term radioactive waste which determines waste density within geological repository. Selective americium separation (EXAm process) by liquid-liquid extraction from a PUREX raffinate was studied. Two experiments were performed in ATALANTE facilities. The first test, on surrogate solution, validated the americium extraction performance. The second trial was carried out in the high-level shielded process line from a genuine PUREX raffinate. Tools used to manage the process are introduced to show performance process achievement." @default.
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• W2031640062 date "2012-01-01" @default.
• W2031640062 modified "2023-09-27" @default.
• W2031640062 title "Implementation of Americium Separation from a PUREX Raffinate" @default.
• W2031640062 doi "https://doi.org/10.1016/j.proche.2012.10.030" @default.
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