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公开(公告)号:US4595529A
公开(公告)日:1986-06-17
申请号:US589241
申请日:1984-03-13
申请人: James C. Neace
发明人: James C. Neace
摘要: Process for removing diluent degradation products from a solvent extraction solution, which has been used to recover uranium and plutonium from spent nuclear fuel. A wash solution and the solvent extraction solution are combined. The wash solution contains (a) water and (b) up to about, and including, 50 volume percent of at least one-polar water-miscible organic solvent based on the total volume of the water and the highly-polar organic solvent. The wash solution also preferably contains at least one inorganic salt. The diluent degradation products dissolve in the highly-polar organic solvent and the organic solvent extraction solvent do not dissolve in the highly-polar organic solvent. The highly-polar organic solvent and the extraction solvent are separated.
摘要翻译: 从用于从废核燃料中回收铀和钚的溶剂萃取溶液中除去稀释剂降解产物的方法。 洗涤溶液和溶剂萃取溶液合并。 基于水和高极性有机溶剂的总体积,洗涤溶液含有(a)水和(b)最多约50体积%的至少一种与极性水混溶的有机溶剂。 洗涤液还优选含有至少一种无机盐。 稀释剂降解产物溶于高极性有机溶剂中,有机溶剂萃取溶剂不溶于高极性有机溶剂。 分离高极性有机溶剂和萃取溶剂。