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四氟化铀和四氟化钍的高温水解

董晓雨 郑小北 宋昱龙 刘玉侠 张岚

核化学与放射化学Issue(3):181-185,5.
核化学与放射化学Issue(3):181-185,5.DOI:10.7538/hhx.2014.36.03.0181

四氟化铀和四氟化钍的高温水解

Pyrohydrolysis of Uranium Tetrafluoride and Thorium Tetrafluoride

董晓雨 1郑小北 2宋昱龙 3刘玉侠 3张岚3

作者信息

  • 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
  • 3. 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
  • 折叠

摘要

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 corre-sponding 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.

关键词

钍基熔盐堆/四氟化铀/四氟化钍/高温水解/溶解

Key words

thorium molten salt reactor/uranium tetrafluoride/thorium tetrafluoride/pyro-hydrolysis/dissolution

分类

能源科技

引用本文复制引用

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,(3):181-185,5.

基金项目

中国科学院战略性先导科技专项(XDA02030000) (XDA02030000)

核化学与放射化学

OA北大核心CSCD

0253-9950

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