张雪松, 夏林路, 张磊, 周世梁, 刘洋. 基于BDMP的某核电厂化容系统上充回路可靠性分析[J]. 核科学与工程, 2022, 42(6): 1354-1361.
引用本文: 张雪松, 夏林路, 张磊, 周世梁, 刘洋. 基于BDMP的某核电厂化容系统上充回路可靠性分析[J]. 核科学与工程, 2022, 42(6): 1354-1361.
ZHANG Xuesong, XIA Linlu, ZHANG Lei, ZHOU Shiliang, LIU Yang. Reliability Analysis of Chemical Volume Control System Charging Loop in a Nuclear Power Plant Based on BDMP[J]. Chinese Journal of Nuclear Science and Engineering, 2022, 42(6): 1354-1361.
Citation: ZHANG Xuesong, XIA Linlu, ZHANG Lei, ZHOU Shiliang, LIU Yang. Reliability Analysis of Chemical Volume Control System Charging Loop in a Nuclear Power Plant Based on BDMP[J]. Chinese Journal of Nuclear Science and Engineering, 2022, 42(6): 1354-1361.

基于BDMP的某核电厂化容系统上充回路可靠性分析

Reliability Analysis of Chemical Volume Control System Charging Loop in a Nuclear Power Plant Based on BDMP

  • 摘要: 核电厂化学与容积控制系统(CVCS)关键组成设备有上充泵、上充阀门组以及热交换器,是保证核电机组安全运行的关键,其运行可靠性对于核安全有重要意义。传统静态故障树不能很好地描述这些动态行为的失效模式,对于此类问题,分析假设过于保守。针对故障树分析的局限性,本研究采用布尔逻辑驱动的马尔可夫过程构建了上充回路的动态可靠性模型,采用KB3进行BDMP建模,分别采用YAMS和PRISM进行不同部分对总不可用率的影响的定量分析。结果表明:系统的总不可用率约为0.033,上充泵失效对系统贡献占比最大约为99.99%,对其采取有针对性的运维措施,以提高核电厂安全水平。

     

    Abstract: The key components of the Chemical and Volumetric Control System(CVCS) for a nuclear power plant are the charging pump, the charging valve set and the heat exchanger, and it is one of the key equipment to ensure the safe operation of nuclear power plant. Its operation reliability is of great significance for nuclear safety. The traditional fault tree analysis lacks the description of time factor, and the analysis assumption is too conservative for this kind of dynamic timeliness problem. Aiming at the limitation of fault tree analysis, this paper uses Boolean logic driven Markov process(BDMP) to build the dynamic reliability model of the charging circuit. KB3 is used to build BDMP model, and YAMS and PRISM are used for quantitative analysis. The influence of different parts on the total unavailability is analyzed. The results show that the total unavailability of the system is about 0.033, and the charging valve failure accounts for about 99.99% of the system. The targeted operation and maintenance measures are taken for each part to improve the safety level of the nuclear power plant and provide reference for the reliability analysis of the chemical capacity system of the nuclear power plant, which has important engineering application value.

     

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