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Volume 44 Issue 5
Oct.  2023
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Li Jianfa, Hua Yongzhen, Liu Feng, Sun Zhongning, Meng Zhaoming. Experimental Investigation on Measuring Leakage Rate of Nuclear Power Plant Containment by Constant Pressure Method[J]. Nuclear Power Engineering, 2023, 44(5): 175-180. doi: 10.13832/j.jnpe.2023.05.0175
Citation: Li Jianfa, Hua Yongzhen, Liu Feng, Sun Zhongning, Meng Zhaoming. Experimental Investigation on Measuring Leakage Rate of Nuclear Power Plant Containment by Constant Pressure Method[J]. Nuclear Power Engineering, 2023, 44(5): 175-180. doi: 10.13832/j.jnpe.2023.05.0175

Experimental Investigation on Measuring Leakage Rate of Nuclear Power Plant Containment by Constant Pressure Method

doi: 10.13832/j.jnpe.2023.05.0175
  • Received Date: 2022-10-18
  • Rev Recd Date: 2023-02-09
  • Publish Date: 2023-10-13
  • In order to further optimize the containment leakage rate measurement scheme and improve the stability and reliability of the measured value, a new leakage rate measurement method, namely the constant pressure method, was developed based on the LabVIEW code in this study. The applicability of the constant pressure method to the leakage rate measurement of the inner containment and the outer containment was confirmed for the first time by carrying out the leakage rate measurement experiment of the large-scale containment simulant. The research shows that the leakage rate measured by the constant pressure method is in good agreement with those measured by traditional pressure drop method, and the relative deviation is less than 5%. For the measurement of the leakage rate of the outer containment, compared with the pressure drop method, the constant pressure method can greatly reduce the measurement time from 10 h to less than 0.8 h on the premise of ensuring the measurement accuracy. The research conclusions can provide theoretical basis for the application of constant pressure method.

     

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  • [1]
    于泾纬,左涛. AP1000安全壳整体泄漏率试验探讨[J]. 中国高新技术企业,2015(16): 38-40.
    [2]
    褚英杰,欧阳钦. 安全壳整体泄漏率计算方法的比较分析[J]. 核动力工程,2010, 31(6): 33-37.
    [3]
    周文权,曲小朋,孟凡彬. 核电站安全壳整体密封性试验方法[J]. 核动力工程,1997,18(2): 58-62.
    [4]
    冯利法,黄海涛. 核电厂钢制安全壳泄漏率测试系统的开发与验证[J]. 核科学与工程,2021, 41(6): 1159-1168.
    [5]
    American Nuclear Society Standards Committee. Containment system leakage testing requirements: ANSI/ANS-56.8-2002[S]. La Grange Park: American Nuclear Society, 2003: 26-28.
    [6]
    KEOGH P. The PWR integrated leak rate test, a review of experiences and results[J]. Nuclear Engineering and Design, 1985, 90(2): 135-141. doi: 10.1016/0029-5493(85)90003-2
    [7]
    欧阳钦,褚英杰. 安全壳整体试验标准ANSI/ANS-56.8-1994在田湾核电厂的应用[J]. 核动力工程,2010, 31(6): 24-28.
    [8]
    沈东明,何锐,张骥. 基于时间序列分析方法对安全壳泄漏率测量阶段的气体弛豫过程研究[J]. 核动力工程,2021, 42(5): 178-181.
    [9]
    沈东明,蔡建涛,何锐,等. 基于统计软件R的安全壳泄漏率试验数据有效性分析[J]. 核动力工程,2020, 41(5): 99-103.
    [10]
    何锐,贾武同,赵健. 安全壳泄漏率测量仪表体积权重分配方法研究[J]. 核动力工程,2015, 36(6): 101-104.
    [11]
    何锐,沈东明,李少纯,等. 双层安全壳环廊泄漏率分析方法研究[J]. 核动力工程,2021, 42(3): 121-125.
    [12]
    朱建斌,刘晓龙. 核电厂安全壳内温度变化对泄漏率测量的影响[J]. 产业与科技论坛,2020, 19(19): 57-58.
    [13]
    李少纯,赵健. 低温对压水堆核电厂安全壳泄漏率测量的影响分析[J]. 中国设备工程,2017(18): 86-88.
    [14]
    郭晓龙. 安全壳泄漏率监测系统日泄漏率异常现象研究[J]. 科技视界,2020(26): 10-13.
    [15]
    刘跃锋,刘祖伦,杨峰,等. 安全壳泄漏率在机组启动阶段的超限分析及处理[J]. 中国核电,2017, 10(3): 399-404.
    [16]
    时朝杰. 核电厂安全壳泄漏率数据增大的分析及处理[J]. 科技视界,2016(8): 95-96.
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