XING Lili, YU Tao, YAN Xuekun, LIU Cuihong, DUAN Zaiyu. 核动力装置回路水中氚监测用于传热管破损诊断的可行性分析[J]. Chinese Journal of Ship Research, 2012, 7(4): 105-107. doi: 10.3969/j.issn.1673-3185.2012.04.018
Citation: XING Lili, YU Tao, YAN Xuekun, LIU Cuihong, DUAN Zaiyu. 核动力装置回路水中氚监测用于传热管破损诊断的可行性分析[J]. Chinese Journal of Ship Research, 2012, 7(4): 105-107. doi: 10.3969/j.issn.1673-3185.2012.04.018

核动力装置回路水中氚监测用于传热管破损诊断的可行性分析

doi: 10.3969/j.issn.1673-3185.2012.04.018
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  • Corresponding author:

    XING Lili

  • Received Date: 2011-12-15
  • Accepted Date: 2012-08-20
  • Rev Recd Date: 2012-04-26
  • Publish Date: 2012-08-25
    © 2012 The Authors. Published by Editorial Office of Chinese Journal of Ship Research. Creative Commons License
    This is an Open Access article distributed under the terms of the Creative Commons Attribution 4.0 International License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
  • 蒸汽发生器传热管易发生破损,对其破损进行监测是反应堆工艺监测的重要内容之一。分析了核动力装置回路水中氚的产生机理及事故情况下氚在回路水中的迁移过程,利用液体闪烁计数器测量了4个核动力装置一、二回路水中氚的放射性活度浓度。结果表明,一回路水净化后的氚放射性活度浓度与相应的二回路水相比高出2个数量级,分别为633,893,188和394倍,可见利用二回路水中氚的放射性活度浓度来监测蒸汽发生器传热管是否发生破损是可行的。后期,还需对氚的在线实时监测开展深入研究。

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