铀、钚氧化物氯化溶解技术进展  

Progress in Chlorination and Dissolution Technology of Oxides of Uranium and Plutonium

作　　者：孟照凯[1] 林如山[1] 陈辉[1] 宋文臣 王长水[1] 何辉[1] 叶国安[1] MENG Zhao-kai;LIN Ru-shan;CHEN Hui;SONG Wen-chen;WANG Chang-shui;HE Hui;YE Guo-an(China Institute of Atomic Energy,P.O.Box 275(26),Beijing 102413,China)

机构地区：[1]中国原子能科学研究院放射化学研究所,北京102413

出　　处：《核化学与放射化学》2022年第3期313-325,I0006,共14页Journal of Nuclear and Radiochemistry

基　　金：中国原子能科学研究院稳定性支持经费科研项目(BJ19001203)。

摘　　要：氧化物的溶解过程是氧化物乏燃料熔盐电解干法后处理工艺的关键步骤,溶解产物将为后续铀钚的分离回收提供原料。氧化物在熔盐体系中溶解度和溶解速率一般较小,为满足工艺需要,通常需要引入氯化试剂。使用不同的氯化试剂,其溶解机理有较大差异。通过广泛的文献调研,分析比较了各种氯化试剂在氯化过程中相关原理及特点,为我国开展铀、钚氧化物氯化溶解的研究提供指导。The dissolution process of oxides is a key step in the pyrochemical process of spent oxide fuel by electrolyzing in molten salt.The dissolved products will provide feeds for subsequent separation and recovery of U and Pu.The solubility and dissolution rate of oxides in molten salt systems are generally low.In order to meet process requirements,it is usually necessary to introduce chlorinating reagents.With different chlorinating reagents,the dissolution mechanism is quite different.Through extensive literature investigation,the related principles and characteristics of various chlorinating reagents in the chlorination process were analyzed and compared,which provided guidance for the research on chlorination and dissolution of U and Pu oxides in China.

关 键 词：铀氧化物 钚氧化物 氯化试剂 氯化溶解 

分 类 号：TL241.2[核科学技术—核燃料循环与材料]