辐射防护 ›› 2021, Vol. 41 ›› Issue (6): 530-535.

• 放射性废物管理 • 上一篇    下一篇

放射性废树脂湿法氧化工艺实验室热试验证

闫晓俊, 柳兆峰, 郭喜良, 席亚慧, 薛海龙, 王志伟   

  1. 中国辐射防护研究院,太原 030006
  • 收稿日期:2021-05-28 出版日期:2021-11-20 发布日期:2021-12-06
  • 通讯作者: 郭喜良。E-mail: guoxl214@126.com
  • 作者简介:闫晓俊(1988—),男,2011年毕业于兰州大学核化工与核燃料工程专业,助理研究员。E-mail: 13935108242@126.com

Laboratory hot test verification of wet oxidation process of radioactive spent resin

YAN Xiaojun, LIU Zhaofeng, GUO Xiliang, XI Yahui, XUE Hailong, WANG Zhiwei   

  1. China Institute for Radiation Protection, Taiyuan 030006
  • Received:2021-05-28 Online:2021-11-20 Published:2021-12-06

摘要: 利用1 kg级废树脂湿法氧化试验台架,采用核电厂产生的实际放射性废树脂开展了1 kg级湿法氧化工艺可行性试验验证,对真实废树脂湿法氧化效果及工艺废气排放安全性进行评估。试验所用废树脂的接触剂量率为602~680 μSv/h,单次试验废树脂处理量为1 kg。结果表明:废树脂采用湿法氧化处理工艺,其分解率大于99%(按物质COD值计算);废树脂湿法氧化过程中,废气对主要核素60Co、54Mn、137Cs和90Sr的载带率低于0.001%。本研究为进一步开展废树脂湿法氧化工艺及装置放大研究奠定了基础。

关键词: 放射性废树脂, 湿法氧化, 工艺验证

Abstract: Using 1 kg spent resin wet oxidation bench, the feasibility hot test of spent resin wet oxidation process was carried out in a nuclear power base. The effect of real spent resin wet oxidation treatment was verified, and the safety of waste gas emission of the process system was evaluated. The contact dose rate of spent resin used in the test is 602-680 Sv/h, and the treatment capacity of spent resin in a single test is 1 kg. The results show that the decomposition rate of spent resin is more than 99% (calculated by COD value), and the carrying rate of tail gas for main nuclides 60Co, 54Mn, 137Cs and 90Sr is less than 0.001%. This study laid a solid foundation for further research on wet oxidation process of spent resin and scale-up of the testing device.

Key words: radioactive spent resin, wet oxidation, process validation

中图分类号: 

  • TL941