Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS Process

Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS Process

In the context of the development of generation IV reactors, solvent extraction process is under development for the reprocessing of spent nuclear fuels. A monoamide extractant was found to be a suitable replacement for TBP. This extractant allows plutonium(IV) back-extraction by changing the acidit...

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Bibliographic Details
Main Authors: Michaud Solenne, Duterme Amandine, Costenoble Sylvain, Lengrand Fabien, Vanel Vincent, Moeyaert Pauline, Sarrat Pierre, Sorel Christian, Miguirditchian Manuel
Format: Article
Language:English
Published: EDP Sciences 2025-01-01
Series:EPJ Web of Conferences
Online Access:https://www.epj-conferences.org/articles/epjconf/pdf/2025/02/epjconf_atalante2025_01005.pdf
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