首页 | 本学科首页   官方微博 | 高级检索  
     

四氟化铀和四氟化钍的高温水解
引用本文:董晓雨,郑小北,宋昱龙,刘玉侠,张岚.四氟化铀和四氟化钍的高温水解[J].核化学与放射化学,2014,36(3):181-185.
作者姓名:董晓雨  郑小北  宋昱龙  刘玉侠  张岚
作者单位:1.中国科学院大学,北京100049;2.中国科学院 上海应用物理研究所 钍基熔盐核能系统研究中心,上海201800
基金项目:中国科学院战略性先导科技专项(XDA02030000)
摘    要:为适应钍基熔盐堆核燃料水法后处理的需求,需将乏燃料中难溶的氟化物转化为相应的氧化物形式,因此提出了高温水解的方法来实现这一目的。研究了UF4、ThF4在不同反应温度和反应时间下的高温水解行为,对其水解产物进行了结构表征和溶解实验的研究。结果表明,UF4、ThF4分别在300℃和350℃即可全部转化为相应的氧化物UO2.25和ThO2。溶解实验结果表明,二者的高温水解产物较易溶解在3mol/L HNO3和Thorex试剂中。

关 键 词:钍基熔盐堆  四氟化铀  四氟化钍  高温水解  溶解  

Pyrohydrolysis of Uranium Tetrafluoride and Thorium Tetrafluoride
DONG Xiao-yu;ZHENG Xiao-bei;SONG Yu-long;LIU Yu-xia;ZHANG Lan.Pyrohydrolysis of Uranium Tetrafluoride and Thorium Tetrafluoride[J].Journal of Nuclear and Radiochemistry,2014,36(3):181-185.
Authors:DONG Xiao-yu;ZHENG Xiao-bei;SONG Yu-long;LIU Yu-xia;ZHANG Lan
Affiliation:1.University of Chinese Academy of Sciences, Beijing 100049, China;2.Center for Thorium Molten Salt Reactor System, Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
Abstract:To meet the needs of the aqueous-reprocessing of used fuel from thorium molten salt reactor, the insoluble fluorides need to be converted into their corresponding oxides form. To realize this, a pyrohydrolysis method was proposed. The pyrohydrolysis behavior of UF4 and ThF4 under different temperature and time was studied, and the structural characterization of the pyrohydrolysis products and the dissolution tests of the products were performed. The results show that, UF4 and ThF4 are entirely converted into their corresponding oxides UO2.25 and ThO2 at 300℃ and 350℃. The results of the dissolution tests show that the pyrohydrolysis products of both UF4 and ThF4 can easily dissolved in 3 mol/L HNO3 and Thorex solution, respectively.
Keywords:thorium molten salt reactor  uranium tetrafluoride  thorium tetrafluoride  pyrohydrolysis  dissolution
本文献已被 CNKI 等数据库收录!
点击此处可从《核化学与放射化学》浏览原始摘要信息
点击此处可从《核化学与放射化学》下载全文
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号