US EPA

4697433 

Journal Article 

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

Vigier, JF; Laplace, A; Renard, C; Miguirditchian, M; Abraham, F 

2018 

Yes 

Journal of Nuclear Materials
ISSN: 0022-3115 

499 

394-400 

10.1016/j.jnucmat.2017.11.028 

WOS:000425106800043 

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 degrees 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 Cl-2. 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). (C) 2017 Elsevier B.V. All rights reserved.