Research on PSA Analysis for Equipment Degradation in Nuclear Power Plant

Zhi Yang, Si-Qi Zhang
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Abstract

It is nowadays a mainstream analysis method to use probability safety analysis (PSA) to support the nuclear power plants (NPPs) daily risk management and safety decision. In China, the NPPs are very experienced in doing PSA evaluation for different plant configurations such as equipment out of operation and failure, etc. In fact, however, the measures often used are not sufficient to reflect the real risk of the unit in such configurations, because there are numerous equipment degradation cases and few complete failure events in the NPPs. On this basis, the paper selects an event related to the main steam safety valve (MSSV) degradation in a domestic NPP as an example, collects failure data through experience feedback, and utilizes mathematical analysis and fitting function to determine the failure potential of the degraded equipment. By PSA calculation, the real unit risk under these configurations will be estimated finally. The purpose of this paper is to provide a new thinking and method for PSA analysis on degraded equipment in the NPPs.
核电站设备退化的PSA分析研究
利用概率安全分析(PSA)来支持核电厂的日常风险管理和安全决策是目前主流的分析方法。在中国,核电站在针对不同电厂配置(如设备停止运行和故障等)进行PSA评估方面经验丰富。然而,事实上,通常使用的措施不足以反映这种配置下机组的真实风险,因为在核电站中有许多设备退化案例和很少的完全故障事件。在此基础上,选取国内某核电站主蒸汽安全阀(MSSV)退化事件为例,通过经验反馈收集失效数据,利用数学分析和拟合函数确定退化设备的失效潜力。通过PSA计算,最终估算出这些配置下的实际单位风险。本文旨在为核电机组退化设备的PSA分析提供一种新的思路和方法。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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