Issue |
EPJ Web Conf.
Volume 317, 2025
6th International ATALANTE Conference on Nuclear Chemistry for Sustainable Fuel Cycles (ATALANTE-2024)
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Article Number | 01005 | |
Number of page(s) | 5 | |
DOI | https://doi.org/10.1051/epjconf/202531701005 | |
Published online | 31 January 2025 |
https://doi.org/10.1051/epjconf/202531701005
Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS Process
CEA, DES, ISEC, DMRC, Univ. Montpellier, Marcoule, Bagnols-sur-Cèze 30207, France
* Corresponding author
Published online: 31 January 2025
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 acidity instead of the plutonium oxidation state. This paper sum up the methodology and the different hot tests performed in Atalante facility to demonstrate uranium(VI)/plutonium(IV) separation from used MOX fuels using this single monoamide extractant with the so-called PUMAS process.
© The Authors, published by EDP Sciences, 2025
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