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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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https://hal-cea.archives-ouvertes.fr/cea-02434002
Contributor : Amplexor Amplexor <>
Submitted on : Thursday, January 9, 2020 - 4:13:49 PM
Last modification on : Monday, January 4, 2021 - 9:16:03 PM

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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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