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

被引:22
|
作者
Vigier, Jean-Francois [1 ,2 ]
Laplace, Annabelle [1 ]
Renard, Catherine [2 ]
Miguirditchian, Manuel [1 ]
Abraham, Francis [2 ]
机构
[1] CEA, Res Dept Min & Fuel Recycling Proc, Nucl Energy Div, F-30207 Bagnols Sur Ceze, France
[2] Univ Lille Nord France, CNRS, ENSCL USTL, UCCS,UMR 8181, BP 90108, F-59652 Villeneuve Dascq, France
关键词
LICL-KCL; PYROCHEMICAL PROCESS; WASTE SALT; PRECIPITATION; ACTINIDES; PU; LANTHANIDES; PRECURSORS; PLUTONIUM; DIAGRAMS;
D O I
10.1016/j.jnucmat.2017.11.028
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
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.
引用
收藏
页码:394 / 400
页数:7
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