铀钚萃取洗涤-共反萃工艺Ⅰ.串级工艺优化  

U,Pu Co-Recovery Process Ⅰ.Cascade Experiments

作　　者：左臣[1] 李传博[1] 晏太红[1] 郑卫芳[1] 张宇[1] 卞晓艳[1] 袁中伟[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：《核化学与放射化学》2013年第4期211-215,共5页Journal of Nuclear and Radiochemistry

基　　金：863课题资助项目(No.2009AA050702)

摘　　要：快堆燃料后处理是实现快堆燃料闭式循环的关键环节之一,快堆乏燃料中裂变产物含量高,进行后处理需要多个铀钚萃取洗涤-共反萃循环才能达到去污效果。本研究针对快堆乏燃料高钚浓度和需要多个萃取洗涤-共反萃循环净化裂变产物的特点,采用模拟料液通过多次串级实验,确定了满足铀钚收率及避免钚聚合的铀钚萃取洗涤-共反萃工艺,实验结果表明,1A铀、钚萃取收率分别为99.995%和99.996%,1B铀、钚反萃收率分别为99.936%和99.996%。FR fuel reprocessing differs from thermal reactor fuel reprocessing in many respects, such as high Pu content, and requires more extraction cycles to give a sufficiently decontamination factor. To elucidate the behavior of uranium and plutonium in extraction/ co-strip process, several cascade experiments were carried out with a simulative solution containing U and Pu. The experiment results show that the yeild of U and Pu in 1A are 99.995% and 99.996%, respectively, the yeild of U and Pu in 1B are 99.936% and 99.996%, respectively. And through the use of dual strip, the possibility of Pu polymerization is reduced by maintaining sufficient acid concentration commensurate with Pu concentration.

关 键 词：快堆燃料后处理 铀钚共反萃 高浓钚 

分 类 号：TL241.14[核科学技术—核燃料循环与材料]