Lab-scale implementation of a next-generation uranium and plutonium separation and purification process from spent nuclear fuel using monoamide solvent - Archive ouverte HAL Access content directly
Conference Papers Year : 2017

Lab-scale implementation of a next-generation uranium and plutonium separation and purification process from spent nuclear fuel using monoamide solvent

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Origin : Files produced by the author(s)
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cea-02434002 , version 1 (09-01-2020)

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  • HAL Id : cea-02434002 , version 1

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S. Costenoble, M.-J. Bollesteros, F. Antegnard, C. Sorel, V. Vanel, et al.. Lab-scale implementation of a next-generation uranium and plutonium separation and purification process from spent nuclear fuel using monoamide solvent. ISEC 2017 (The 21st International Solvent Extraction Conference), Nov 2017, Miyazaki, Japan. ⟨cea-02434002⟩

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