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Article Dans Une Revue Journal of Nuclear Materials Année : 2018

Uranium (III)-Plutonium (III) co-precipitation in molten chloride


Co-management of the actinides in an integrated closed fuel cycle by a pyrochemical process is studied at the laboratory scale in France in the CEA-ATALANTE facility. In this context the co-precipitation of U(III) and Pu(III) by wet argon sparging in LiCl-CaCl2 (30–70 mol%) molten salt at 705 °C is studied. Pu(III) is prepared in situ in the molten salt by carbochlorination of PuO2 and U(III) is then introduced as UCl3 after chlorine purge by argon to avoid any oxidation of uranium up to U(VI) by Cl2. The oxide conversion yield through wet argon sparging is quantitative. However, the preferential oxidation of U(III) in comparison to Pu(III) is responsible for a successive conversion of the two actinides, giving a mixture of UO2 and PuO2 oxides. Surprisingly, the conversion of sole Pu(III) in the same conditions leads to a mixture of PuO2 and PuOCl, characteristic of a partial oxidation of Pu(III) to Pu(IV). This is in contrast with coconversion of U(III)-Pu(III) mixtures but in agreement with the conversion of Ce(III).


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Dates et versions

hal-03169455 , version 1 (15-03-2021)



Jean-François Vigier, Annabelle Laplace, Catherine Renard, Manuel Miguirditchian, Francis Abraham. Uranium (III)-Plutonium (III) co-precipitation in molten chloride. Journal of Nuclear Materials, 2018, Journal of Nuclear Materials, 499, pp.394-400. ⟨10.1016/j.jnucmat.2017.11.028⟩. ⟨hal-03169455⟩
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