氟盐在液态氟化氢中的溶解分离研究
发布时间：2018-08-25 20:01
【摘要】：载体盐~7LiF的回收是熔盐堆核燃料后处理的重要环节。提出了一种利用氢氟酸溶解技术实现熔盐堆干法处理尾料中LiF分离回收的工艺。首先考察了氢氟酸浓度、溶解时间和溶解温度对LiF及ThF_4在氢氟酸中溶解的影响,得到LiF与ThF_4分离的最优溶解分离工艺条件,并对其溶解机制做了初步探讨。随后进行了混合氟盐中LiF的分离回收实验,结果表明LiF的收率在95%以上,产品LiF纯度在97%以上。
[Abstract]:The recovery of carrier salt 7 lif is an important step in the reprocessing of molten salt reactor nuclear fuel. A process of separating and recovering LiF from tailings by using hydrofluoric acid dissolution technology was proposed. Firstly, the effects of hydrofluoric acid concentration, dissolution time and dissolution temperature on the dissolution of LiF and ThF_4 in hydrofluoric acid were investigated. The optimum conditions for the dissolution and separation of LiF and ThF_4 were obtained, and the dissolution mechanism was preliminarily discussed. The results showed that the yield of LiF was over 95% and the purity of LiF was over 97%.
【作者单位】： 中国科学院上海应用物理研究所;
【分类号】：TL24;TQ131.11
本文编号：2203954
[Abstract]:The recovery of carrier salt 7 lif is an important step in the reprocessing of molten salt reactor nuclear fuel. A process of separating and recovering LiF from tailings by using hydrofluoric acid dissolution technology was proposed. Firstly, the effects of hydrofluoric acid concentration, dissolution time and dissolution temperature on the dissolution of LiF and ThF_4 in hydrofluoric acid were investigated. The optimum conditions for the dissolution and separation of LiF and ThF_4 were obtained, and the dissolution mechanism was preliminarily discussed. The results showed that the yield of LiF was over 95% and the purity of LiF was over 97%.
【作者单位】： 中国科学院上海应用物理研究所;
【分类号】：TL24;TQ131.11
【参考文献】
相关期刊论文 前1条
1 郭志锋;;钍基燃料循环的发展与展望[J];国外核新闻;2008年01期
【共引文献】
相关期刊论文 前4条
1 宋昱龙;李峥;刘玉侠;张岚;;氟盐在液态氟化氢中的溶解分离研究[J];无机盐工业;2017年08期
2 梁春恬;窦元佳;;核子与~(232)Th反应的色散耦合道光学势研究[J];天津城市建设学院学报;2013年02期
3 江绵恒;徐洪杰;戴志敏;;未来先进核裂变能——TMSR核能系统[J];中国科学院院刊;2012年03期
4 冷伏海;刘小平;李泽霞;黄龙光;王林;王海燕;周丽英;;钍基核燃料循环国际发展态势分析[J];科学观察;2011年06期
，本文编号：2203954
本文链接：https://www.wllwen.com/kejilunwen/huaxuehuagong/2203954.html
