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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

S. Costenoble 1 M.-J. Bollesteros 1 F. Antegnard 1 C. Sorel 1 V. Vanel 1 M. Montuir 1 M. Miguirditchian 1 X. Heres 1 V. Boyer-Deslys 1 S. Grandjean 1
1 CEA-DES (ex-DEN) - CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire)
Keywords : spent nuclear fuel monoamide liquid-liquid extraction Uranium-plutonium separation
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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 : Tuesday, April 28, 2020 - 11:28:15 AM

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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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