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某EPR 核电站蒸汽发生器给水系统单点跳堆风险分析及控制逻辑冗余改造

Risk Analysis of Single-Point Reactor Trip in the Steam Generator Feedwater System of an EPR Nuclear Power Plant and Redundancy Retrofit of Control Logic

  • 摘要: 蒸汽发生器主给水系统(ARE)是核电站二回路的关键系统,其控制逻辑的可靠性直接影响机组安全。某EPR 核电站1、2 号机组ARE 系统在运行中暴露出因单一仪表故障(如ARE窄量程压力变送器)导致跳堆的风险,且部分控制信号硬接线缺乏冗余设计。本文系统分析了上述失效模式,并提出了基于控制逻辑优化与硬接线冗余的综合改造方案。本研究成果可为同类核电机组的控制逻辑优化提供技术参考。

     

    Abstract: The Steam Generator Main Feedwater System (ARE) is a critical system in the secondary circuit of a nuclear power plant, and the reliability of its control logic directly affects unit safety. During operation, the ARE systems of Units 1 and 2 at a certain EPR nuclear power plant were found to be at risk of reactor trip caused by a single instrument failure (e.g., the ARE narrow-range pressure transmitter), and some hardwired control signals lacked redundancy design. This paper systematically analyzes the aforementioned failure modes and proposes a comprehensive retrofit scheme based on control logic optimization and hardwired redundancy. The research findings can provide technical references for the control logic optimization of similar nuclear power units.

     

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