铀钚萃取洗涤-共反萃工艺的离心萃取器台架实验研究  

Rig Trial Study on U and Pu Co-recovery Process in Centrifugal Contactor

作　　者：左臣[1] 李传博[1] 晏太红[1] 郑卫芳[1] 袁中伟[1] 曹智[1] 孙雪梅[1] 

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：《原子能科学技术》2015年第6期992-996,共5页Atomic Energy Science and Technology

基　　金：863计划资助项目(2009AA050702)

摘　　要：由于快堆MOX乏燃料放射性强,需要缩短停留时间以降低溶剂辐解,本工作以离心萃取器为萃取设备,在短停留时间下进行了快堆MOX乏燃料后处理铀钚萃取洗涤-共反萃工艺研究。研究结果显示,该工艺在单级停留时间约20s时具有良好的铀钚收率,萃取洗涤过程中铀和钚收率均大于99.99%,共反萃过程中铀和钚收率分别为99.99%和99.94%;同时能有效防止第三相的形成,避免钚的聚合沉淀。The high specific activity of fast reactor MOX spent fuel will leads to serious solvent degradation ,so the contact time needs to be shorten .A rig trial of U and Pu co‐recovery process was performed in centrifugal contactor .The results show that when contact time in single stage is 20 s ,the yields of U and Pu in extraction‐scrub process are higher than 99.99% , respectively , and the yields of U and Pu in co‐stripping process are 99.99% and 99.94% ,respectively .The risk of the third phase generation and polymerization and precipitation of Pu can be prevented .

关 键 词：MOX乏燃料 后处理 铀钚萃取洗涤-共反萃 离心萃取器 

分 类 号：TL364.5[核科学技术—核技术及应用]