基于增强组件连接法的核电厂EHR DFT系统活性堆坑泛函可靠性分析

D. Guo, Shaoxuan Wang, Daochuan Ge, L. Tong, Xuewu Cao
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引用次数: 0

摘要

作为核电厂安全关键系统的复杂系统,冗余设计常用于提高系统的可靠性。核电厂安全关键系统由于冗余设计和管理策略的原因,往往具有复杂的连续失效行为。对于具有连续失效行为的核电厂安全关键系统,在给定任务时间内对其可靠性进行评估是非常重要的。本文采用动态故障树(DFT)对某核电站安全壳排热系统(EHR)的主动堆坑泛洪函数进行建模,并用BDD方法对其进行分析。为了构建BDD,提出了一种增强的基于组件连接的方法。分析了活性反应堆坑淹函数的失效概率。此外,还对电子病历设备的FV、RAW和RRW重要性进行了评价。结果表明,在任务时间24小时内的累积失效概率为1.81E−05,非常低。列车A(列车B)的累计失效概率为4.25E−03。结果表明,在24h的任务时间下,EHR的活性反应堆坑淹函数具有很高的可靠性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method
Redundancy design is often used to enhance the reliability of complex systems which often run as safety-critical systems of nuclear power plant (NPP). Due to the redundancy design and management strategies, safety-critical systems of a NPP often have complex sequential failure behaviors. For a safety-critical system of a NPP with sequential failure behaviors, it is very important to evaluate its reliability for a given mission time. In this paper, the active reactor pit flooding function of EHR (containment heat removal system) of a nuclear power plant (NPP) is modeled by dynamic fault tree (DFT) and analyzed by BDD. To build the BDD, an enhanced component-connection-based method is proposed. The failure probability of the active reactor pit flooding function is analyzed. Besides, the FV, RAW and RRW importance of the EHR equipment are also evaluated. The results show the cumulative failure probability at mission time 24 hour is 1.81E−05, which is very low. The cumulative failure probability of train A (train B) is 4.25E−03. It can be concluded that the active reactor pit flooding function of EHR has a very high reliability given a mission time 24h.
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