• 품질경영학회지
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• 제46권2호
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• pp.327-338
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• 2018

Purpose: A risk evaluation procedure is proposed for common failure causes in FMEA(Failure Mode and Effects Analysis). The conventional FMEA does not provide a proper means to compare common failure causes with other failure causes. This research aims to develop a risk evaluation procedure in FMEA where common failure causes and other failure causes exist together. Methods: For each common failure cause, the effect of each combination of its resulting failures is recommended to be reevaluated considering their interactive worsening effect. And the probability that each combination of failures is incurred by the same common cause is also considered. Based on these two factors, the severity of each common cause is determined. Other procedures are similar to the conventional method. Results: The proposed procedure enables to compare and prioritize every failure cause. Thus, the common causes, each of which incurring two or more failures, and other causes, each of which is corresponding to one failure, can be fairly compared. Conclusion: A fair and proper way of comparing the common failure causes and other causes is provided. The procedure is somewhat complicated and requires more works to do. But it is worth to do.

• 한국철도학회:학술대회논문집
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• 한국철도학회 2008년도 추계학술대회 논문집
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• pp.255-262
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• 2008

The railway is required to be highly reliable, which carries a lot of passenger and baggage. Presently, the reliability prediction method is based on independent failure. If the common cause failure affecting many components simultaneously in a system occurs, the system has seriously an aptitude to be broken out. Therefore, for raising the reliability of the railway power system, it is introduced that the analysis is conducted to use the common cause failure. The common cause failure is modeled and is combined with independent failure. Furthermore in order to examine the method, it is applied to the railway power substation. If this method is used to the power system, the reliability of the railway power system will be highly improved.

• 산업공학
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• 제25권4호
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• pp.382-392
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• 2012

Reactor protection system to keep nuclear safety and operational economy of plants requires high reliability. Such a high reliability of the system can be achieved through the redundant design of components. However, common cause failures of components reduce the benefits of redundant design. Thus, the common cause failure analysis, to accurately calculate the reliability of the reactor protection system, is carried out using alpha-factor model. Analysis results to 24 operating months are that 1) the system reliability satisfies the reliability goal of EPRI-URD and 2) the common cause failure contributes 90% of the system unreliability. The uncertainty analysis using alpha factor parameters of 0.05 and 0.95 quantile values shows significantly large difference in the system unreliability.

• International Journal of Reliability and Applications
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• 제11권2호
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• pp.123-138
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• 2010

This paper investigates a mathematical model of a system composed of two non-identical unit parallel system with common-cause failure, critical human error, non-critical human error, preventive maintenance and two type of repair, i.e. cheaper and costlier. This system goes for preventive maintenance at random epochs. We assume that the failure, repair and maintenance times are independent random variables. The failure rates, repair rates and preventive maintenance rate are constant for each unit. The system is analyzed by using the graphical evaluation and review technique (GERT) to obtain various related measures and we study the effect of the preventive maintenance preventive maintenance on the system performance. Certain important results have been derived as special cases. The plots for the mean time to system failure and the steady-state availability A(${\infty}$) of the system are drawn for different parametric values.

• Nuclear Engineering and Technology
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• 제24권1호
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• pp.14-29
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• 1992

원자력 발전소에서 발생하는 공통원인 고장을 분석하기 위한 컴퓨터 코드 COMCAF를 개발하였다. 공통원인 고장을 다룰 때, 먼저 계통의 최소 단절집합들을 공통원인 기본사상들이 고려되지 않은 고장수목으로부터 구한다. 그리고, 공통원인 고장들이 같은 최소 단절집합내의 부품들간에 있는지 또는 서로 다른 최소 단절집합들의 부품들간에 있는지를 고려하여 이들 최소 단절집합들의 발생 확률값을 계산한다. 유사하거나 동일한 부품들간에 공통원인 고장이 있을때는 Basic Para-meter 모델을 사용한다. 그러나, 서로 다른 부품들간에 공통원인 고장이 있을때는 Basic Para-meter모델에 쓰인 Symmetry Assumption을 두개 이상의 부품에 영향을 주는 기본사상들에만 적용한다. Inclusion-Exclusion방법을 사용하여 정점사상확률간을 구한다. 이 경우 같은 최소 단절 집합들에 있는 부품들의 공통원인 고장뿐만아니라 서로 다른 최소 단절집합들에 있는 부품들의 공통원인 고장도 쉽게 고려될 수 있다. 본 연구에서는 이러한 공통원인 고장분석을 가압경수로의 보조 급수계통에 적용하였다. 이들 정점사상의 확률값들을 공통원인 고장이 없는 경우와 비교하였다.

• 한국경영과학회지
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• 제30권2호
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• pp.63-71
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• 2005

In the field of nuclear reactor safety study, common cause failures (CCFs) became significant contributors to system failure probability and core damage frequency in most Probabilistic risk assessments. However, it is hard to estimate the reliability of such a system, because of the dependency of components caused by CCFs. In order to analyze the system, we propose an analytic method that can find the parameters with lack of raw data. This study adopts the shock model in which the failure probability increases as the shock is cumulated. We use two-step Expectation and Maximization (EM) algorithm to find the unknown parameters. In order to verify the analysis result, we perform the simulation under same environment. This approach might be helpful to build the defensive strategy for the CCFs.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2001년도 춘계학술대회 논문집
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• pp.324-327
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• 2001

This paper shows an example of the Design Review and Common-Cause Failure (CCF) Modeling of mechanical Parts. Reliability should be continuously monitored during the entire period of design. Design Review is the procedure to improve the reliability for the product. We proposed the reliability assessment and design review method. CCF Model is the general dependent model considering the failure mode effects several component simultaneously. This study considers the computation of the network with dependent components. It is important that CCF model is applied for mechanical pars.

• 조명전기설비학회논문지
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• 제25권9호
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• pp.62-68
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• 2011

Power system needs to sustain high reliability due to its complexity and security. The reliability prediction method is usually based on independent failure. However, in practice, the Common Cause Failures(CCF) and Cascading failure occur to the facilities in power system as well as independent failures in many cases. The CCF and Cascading failure turn out the system collapse seriously in a wide range. Therefore to improve the reliability of the power system practically, it is required that the analysis is conducted by using the CCF and Cascading failure. This paper describes the CCF and Cascading failure modeling combined with independent failure. The incorporated model of independent failure, CCF and cascading failure is proposed and analyzed, and it is applied to the distribution power system in order to examine this method.

• Nuclear Engineering and Technology
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• 제53권2호
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• pp.357-367
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• 2021

In general, common cause failures (CCFs) have been modeled with the assumption that components within the same group are symmetric. This assumption reduces the number of parameters required for the CCF probability estimation and allows us to use a parametric model, such as the alpha factor model. Although there are various asymmetric conditions in nuclear power plants (NPPs) to be addressed, the traditional CCF models are limited to symmetric conditions. Therefore, this paper proposes the copulabased CCF model to deal with asymmetric as well as symmetric CCFs. Once a joint distribution between the components is constructed using copulas, the proposed model is able to provide the probability of common cause basic events (CCBEs) by formulating a system of equations without symmetry assumptions. In addition, Bayesian inferences for the parameters of the marginal and copula distributions are introduced and Markov Chain Monte Carlo (MCMC) algorithms are employed to sample from the posterior distribution. Three example cases using simulated data, including asymmetry conditions in total failure probabilities and/or dependencies, are illustrated. Consequently, the copula-based CCF model provides appropriate estimates of CCFs for asymmetric conditions. This paper also discusses the limitations and notes on the proposed method.

• 대한기계학회논문집A
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• 제36권4호
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• pp.373-378
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• 2012

본 논문에서는 공통원인고장을 고려하여 증기터빈 비산확률을 평가하였다. 이 과정에서 저속 및 고속에서 터빈 비산물 발생 경로를 제시하고, 고장수목을 활용하여 비산물 발생빈도를 구하였다. 공통원인고 장을 고려하기 위해서 Alpha Factor 방법론을 사용하였다. 순차 및 비순차 시험에 대해서 각각의 빈도를 비교분석 하였으며, 불확실성을 평가하였다. (1) 고속회전에 의한 연성파괴로 발생하는 터빈비산물 방출빈도는 8.005E-7/year로 평가되었다. (2) 만약, 공통원인고장이 고려되면, 시험방식에 따라 11% 및 33%의 방출빈도 증가를 확인하였다. (3) 사용된 CCF 변수의 불확실성을 고려하면, 터빈방출빈도는 90%의 신뢰도 기준 9.35E-7에서 1.13E-6 사이에 존재함을 알 수 있었다.