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APPLICATION OF FAULT TREE METHODOLOGY TO MODELING OF THE AP1000~? PLANT DIGITAL REACTOR PROTECTION SYSTEM

机译:故障树方法在AP1000建模中的应用〜?植物数字反应器保护系统

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The reactor trip system (RTS) and engineered safety features actuation system (ESFAS) in nuclear power plants utilizes instrumentation and control (I&C) to provide automatic protection against unsafe and improper reactor operation during steady-state and transient power operations. During normal operating conditions, various plant parameters are continuously monitored to assure that the plant is operating in a safe state. In response to deviations of these parameters from pre-determined set points, the protection system will initiate actions required to maintain the reactor in a safe state. These actions may include shutting down the reactor by opening the reactor trip breakers and actuation of safety equipment based on the situation. The RTS and ESFAS are represented in probabilistic risk assessments (PRAs) to reflect the impact of their contribution to core damage frequency (CDF). The reactor protection systems (RPS) in existing nuclear power plants are generally analog based and there is general consensus within the PRA community on fault tree modeling of these systems. In new plants, such as AP1000~? plant, the RPS is based on digital technology. Digital systems are more complex combinations of hardware components and software. This combination of complex hardware and software can result in the presence of faults and failure modes unique to a digital RPS. The United States Nuclear Regulatory Commission (NRC) is currently performing research on the development of probabilistic models for digital systems for inclusion in PRAs; however, no consensus methodology exists at this time. Westinghouse is currently updating the AP1000~? plant PRA to support initial operation of plants currently under construction in the United States. The digital RPS is modeled using fault tree methodology similar to that used for analog based systems. This paper presents high level descriptions of a typical analog based RPS and of the AP1000? plant digital RPS. Application of current fault tree modeling techniques to the digital system is reviewed, and unique issues related to accounting for common cause failures and software failures are discussed.
机译:核电厂中的反应堆跳闸系统(RTS)和工程安全功能驱动系统(ESFA)利用仪器控制和控制(I&C),以在稳态和瞬态电源操作期间自动保护免受不安全和不正当的反应器操作。在正常操作条件下,连续监测各种植物参数以确保工厂以安全状态运行。响应于这些参数从预定设定点的偏差,保护系统将启动在安全状态下维护反应器所需的动作。这些动作可以包括通过打开反应器跳闸断路器和基于情况的安全设备致动来关闭反应器。 RTS和ESFA在概率风险评估(PRA)中表示,以反映其对核心损伤频率(CDF)的贡献的影响。现有核电站的反应器保护系统(RPS)通常是基于类似的,并且在PRA社区内有一般的共识,这些系统的故障树建模是。在新植物中,如ap1000〜?植物,RPS基于数字技术。数字系统更复杂的硬件组件和软件的组合。这种复杂硬件和软件的组合可能导致存在数字RPS独特的故障和故障模式。美国核监管委员会(NRC)目前正在对数字系统纳入PRA的概率模型进行研究;但是,此时没有共识的方法存在。 Westinghouse目前正在更新AP1000〜吗?工厂PRA支持目前正在建设中的植物的初始操作。数字RPS采用类似于基于模拟系统的故障树方法进行建模。本文介绍了典型的基于模拟RP和AP1000的高级描述?植物数字rps。讨论了当前故障树建模技术对数字系统的应用,并讨论了与常见原因失败和软件故障有关的唯一问题。

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