Modeling of common cause failures (CCFs) by using beta factor parametric model

Qazi Muhammad Nouman Amjad, M. Zubair, G. Heo
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引用次数: 6

Abstract

Nuclear accidents and incidents such as Three Mile Island (TMI-2) accident (1979), Chernobyl disaster (1986) and the recent Fukushima nuclear disaster (2011) have caused people to be suspicious of the safety of nuclear energy, and have reduced the level of trust among public. Common cause failure (CCF) has been a major element of such accidents in terrestrial nuclear power reactors because of high redundancy built into the systems and susceptibility of these redundant systems to CCF mechanisms. For this purpose, ad hoc approaches used to be taken to address vulnerabilities to CCF by operating staff of the plants. A CCF event is a result of simultaneous failure of two or more individual components. Such an event can significantly affect the availability of safety systems and has long been recognized as an important issue in the probabilistic safety assessment (PSA). So a complicated and unresolved problem in the subject of safety and reliability is to model CCF in PSA. To overcome this problem the present research highlights a mathematical model to estimate system unavailability in nuclear power plants (NPPs) as well as in other industries. This mathematical model is based on Beta Factor parametric model. The motivation for development of this model lays in the fact that one of the most widespread software such as for fault tree (FT) and event tree (ET) modeling as part of the PSA does not comprise the option for simultaneous assignment of single failure event to multiple CCF groups. A significant finding from such modeling is that, in contrast to common expectations, a too early nuclear phase-out will not serve the deployment of renewable energy sources and rational use of energy. The proposed method can be seen as an advantage of the explicit modeling of CCF.
用β因子参数模型对共因故障进行建模
1979年的三哩岛(TMI-2)事故、1986年的切尔诺贝利(Chernobyl)灾难以及2011年的福岛(Fukushima)核灾难等核事故和事件使人们对核能的安全性产生了怀疑,并降低了公众对核能的信任水平。共因故障(CCF)一直是陆地核动力反应堆事故的主要因素,因为系统内置的高冗余性以及这些冗余系统对CCF机制的敏感性。为此目的,过去常常采取特别的方法来解决电厂操作人员对CCF的脆弱性。CCF事件是两个或多个单独部件同时失效的结果。此类事件会严重影响安全系统的可用性,长期以来一直被认为是概率安全评估(PSA)中的一个重要问题。因此,在安全可靠性研究中,CCF模型的建立是一个复杂而尚未解决的问题。为了克服这个问题,本研究强调了一个数学模型来估计核电厂(NPPs)以及其他工业中的系统不可用性。该数学模型基于Beta因子参数模型。开发该模型的动机在于,作为PSA的一部分,最广泛的软件之一,如故障树(FT)和事件树(ET)建模,不包括将单个故障事件同时分配给多个CCF组的选项。这种模型的一个重要发现是,与普遍预期相反,过早地逐步淘汰核能将不利于可再生能源的部署和能源的合理使用。该方法可以看作是CCF显式建模的一个优点。
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