氦-3回路中氚的辐射安全分析

辐射防护 ›› 2020, Vol. 40 ›› Issue (2): 104-109.

氦-3回路中氚的辐射安全分析

李炳林^1,2

1.西南石油大学机电工程学院,成都 610500;
2.中国核动力研究设计院一所,成都 610213

收稿日期:2018-07-12 发布日期:2020-05-15
作者简介:李炳林(1982—),男,2007年本科毕业于长春理工大学过程装备与控制工程专业,2012年博士毕业于华中科技大学机械设计及理论专业,副研究员。E-mail:lubay600@sina.com

Radiation safety analysis on tritium exposure of He-3 loop

LI Binglin^1,2

1. Mechatronic Engineering College, Southwest Petroleum University, Chengdu 610500;
2. The First Sub-institute, Nuclear Power Institute of China, Chengdu 610041

Received:2018-07-12 Published:2020-05-15

摘要/Abstract

摘要： 氚安全是确保燃料元件堆内功率瞬态试验的关键因素之一。本文首先分析了氚的来源和危害,提出了氦-3回路氚的防护和去污措施,然后讨论了氚在正常运行和事故时释放到包容箱和工艺间的量和处理措施,最后评价了氦-3系统发生不同安全措施失效的事故情况下工作人员的氚内照射剂量。结果表明:系统正常运行时工作人员所受最大剂量为1.27 μSv/d,除了氚安全措施全部同时失效且HT短时间全部被氧化成HTO的极限事故以外,在一般事故情况下氚对工作人员产生的最大剂量小于10 mSv。

关键词: 氦-3回路, 氚安全, 内照射, 剂量计算

Abstract: The use of He-3 loop for power transient test of LWR fuel element raises tritium safety issues due to occupational exposure. This paper proposed some protection programs of tritium and the tritium decontamination in He-3 loop, and analysed the tritium source term and the hazard of the tritiated water vapor. Then, the normal and accidental release rates of tritium from He-3 loop into the glove-box and working area are discussed. The released tritium can be treated safely. Finally, the intake doses for internal exposure of tritium are calculated through each pathway based on the failures of He-3 system safety measures. The results show the maximum individual doses to the operator are 1.27 μSv/d in normal operation and less than 10 mSv if not all the protective precautions fail or loss simultaneously in an extreme accident case.

Key words: He-3 loop, tritium safety, internal exposure, dose assessment

中图分类号:

X822.7

李炳林. 氦-3回路中氚的辐射安全分析[J]. 辐射防护, 2020, 40(2): 104-109.

LI Binglin. Radiation safety analysis on tritium exposure of He-3 loop[J]. RADIATION PROTECTION, 2020, 40(2): 104-109.