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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| Format: | Article |
| Language: | English |
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EDP Sciences
2025-01-01
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| 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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| author | Michaud Solenne Duterme Amandine Costenoble Sylvain Lengrand Fabien Vanel Vincent Moeyaert Pauline Sarrat Pierre Sorel Christian Miguirditchian Manuel |
| author_facet | Michaud Solenne Duterme Amandine Costenoble Sylvain Lengrand Fabien Vanel Vincent Moeyaert Pauline Sarrat Pierre Sorel Christian Miguirditchian Manuel |
| author_sort | Michaud Solenne |
| collection | DOAJ |
| description | 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. |
| format | Article |
| id | doaj-art-06e6513e03b045728577da62a1559d75 |
| institution | Kabale University |
| issn | 2100-014X |
| language | English |
| publishDate | 2025-01-01 |
| publisher | EDP Sciences |
| record_format | Article |
| series | EPJ Web of Conferences |
| spelling | doaj-art-06e6513e03b045728577da62a1559d752025-02-05T10:53:04ZengEDP SciencesEPJ Web of Conferences2100-014X2025-01-013170100510.1051/epjconf/202531701005epjconf_atalante2025_01005Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS ProcessMichaud Solenne0Duterme Amandine1Costenoble Sylvain2Lengrand Fabien3Vanel Vincent4Moeyaert Pauline5Sarrat Pierre6Sorel Christian7Miguirditchian Manuel8CEA, DES, ISEC, DMRC, Univ. Montpellier, MarcouleCEA, DES, ISEC, DMRC, Univ. Montpellier, MarcouleCEA, DES, ISEC, DMRC, Univ. Montpellier, MarcouleCEA, DES, ISEC, DMRC, Univ. Montpellier, MarcouleCEA, DES, ISEC, DMRC, Univ. Montpellier, MarcouleCEA, DES, ISEC, DMRC, Univ. Montpellier, MarcouleCEA, DES, ISEC, DMRC, Univ. Montpellier, MarcouleCEA, DES, ISEC, DMRC, Univ. Montpellier, MarcouleCEA, DES, ISEC, DMRC, Univ. Montpellier, MarcouleIn 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.https://www.epj-conferences.org/articles/epjconf/pdf/2025/02/epjconf_atalante2025_01005.pdf |
| spellingShingle | Michaud Solenne Duterme Amandine Costenoble Sylvain Lengrand Fabien Vanel Vincent Moeyaert Pauline Sarrat Pierre Sorel Christian Miguirditchian Manuel Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS Process EPJ Web of Conferences |
| title | Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS Process |
| title_full | Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS Process |
| title_fullStr | Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS Process |
| title_full_unstemmed | Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS Process |
| title_short | Uranium(VI)/Plutonium(IV) Separation from Spent MOX Fuels Using a Single Monoamide Extractant: The PUMAS Process |
| title_sort | uranium vi plutonium iv separation from spent mox fuels using a single monoamide extractant the pumas process |
| url | https://www.epj-conferences.org/articles/epjconf/pdf/2025/02/epjconf_atalante2025_01005.pdf |
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