• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.193.2-193
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• 2002

• JOURNAL OF ELECTRICAL WORLD
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• s.261
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• pp.70-76
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• 1998

철도분야에서의 전기$\cdot$신호설비 고장은 열차의 정상운행에 차질을 일으켜 사회적으로 커다란 영향을 끼치게 되므로 설비의 유지관리를 위해서는 많은 노력이 필요하다. 또 이러한 보전작업에는 철도 설비가 널리 산재되어 있기 때문에 이동을 수반하는 작업, 열차가 통과하지 않는 야간 작업, 만일의 경우 위험을 수반하는 작업 등, 이 분야 특유의 작업이 있다. 한편 보전작업에 종사하는 기술자는 해마다 줄어들고 있으며 앞으로 젊은 근로자의 부족은 더욱더 심해질 것으로 보인다. 그러한 이유로 설비보전의 자력화, 미연의 고장방지, 고장의 조기복구와 재발방지를 목표로 지금까지 사람의 손에 의지해 오던 설비보전을 기계화하고 자동화하는 시스템을 개발하게 되었다. 이 시스템은 대상설비에 따라 다음의 3가지 시스템으로 분류된다. $\cdot$신호설비 보전시스템 $\cdot$변전$\cdot$수배전설비 보전시스템$\cdot$연선전기설비 보전시스템 이들시스템에 공통적인 주요 특징을 들면 아래와 같다. (1)사고를 미연에 방지하고 사고원인을 규명 이벤트발생 전후의 변화나 중장기트렌드를 원격감시할 수 있다. (2)시스템의 변경$\cdot$증설이 용이 인텔리전트단말에 의하여 처리를 계층화하였기 때문에 빌딩블록식으로 시스템을 확장할 수 있다. (3)경제적인 시스템 필드 네트워크의 채용으로 공사비를 삭감할 수 있다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05a
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• pp.520-526
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• 1997

WASH-1400[1]이 발간된 이후 수행되어왔던 많은 확률론적 안전성 평가 결과를 보면 노심손상빈도를 나타내는 사고경위 중 많은 부분이 인간행위와 관련이 있는 것으로 밝혀져 확률론적 안전성 평가에서 인간행위를 다루는 것은 매우 중요하게 되었다. 그러나 인간신뢰도분석은 인간행위의 다변성(variability)으로 인해 인간행위의 모델링이 어렵고 데이타가 부족해 뚜렷한 방법론이 없어 분석시 분석자의 주관성이 개입될 여지가 있고 분석결과에는 많은 불확실성을 포함하고 있다. 노심손상빈도를 나타내는 사고경위에는 다수 인간행위가 있는 포함돼있는 단절집합을 얻게되는데 이러한 인간행위들 사이에는 기기의 공통원인 고장처럼 의존성이 존재한다. 이러한 의존성의 평가방법 또한 뚜렷하게 설정되어 있지 않은 형편이다. 이에 본 논문에서는 월성 2,3,4호기 확률론적 안전성 평가 모델에 고려되어있는 인간행위들의 인간오류 확률 값과 의존성 수준의 변화에 대한 민감도분석을 수행하였다. 분석결과 초기사건 이후의 인간행위가 노심손상빈도 변화에 크게 기여하는 것이 밝혀졌고, 다수 인간행위들 사이의 의존성 수준변화가 노심손상빈도 변화에 큰 영향을 준다는 것이 밝혀졌다.

• Journal of the Korean Operations Research and Management Science Society
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• v.30 no.2
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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.

• Journal of the Korean Society for Aeronautical & Space Sciences
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• v.50 no.4
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• pp.259-267
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• 2022

The existing method of deriving the fail-safe design requirements for the domestic developed rotary-wing aircraft system may miss the factors that cause critical system function failures, when being applied to the latest integrated avionics system. It is because the existing method analyzes the severity effect of the failures caused by a single item. To solve the issue, we present a systematic analysis procedure for deriving fail-safe design requirements of system architecture by utilizing functional hazard assessment and development assurance level analysis of SAE ARP4754A, international standard for complex system development. To demonstrate that our proposed procedure can be a solution for the aforementioned issue, we set up experimental environments that include common factors that can cause critical function failures of a system, and we conducted a cross-validation with the existing method. As a result, we showed that the proposed procedure can identify the potential critical common factors that the existing method have missed, and that the proposed procedure can derive fail-safe design requirements to control the common factors.

• Journal of Korean Society for Quality Management
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• v.46 no.2
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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.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.10 no.1
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• pp.51-55
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• 2014

Based on the results of Probabilistic Safety Assessment(PSA) for a Nuclear Power Plant (NPP), Common Cause Failure(CCF) events have been recognized as one of the main contributors to the risk. Also, the CCF data and estimation method used in domestic PSA models have been pointed out as an issue with respect to the quality. The existing method of MGL and non-staggered testing even widely used were considered conservative in estimating the safety and had a limited capability in uncertainty analyses. Therefore, this paper presents the CCF estimation using a new generic data source and Alpha factor method. The analyses showed that Alpha factor and staggered method are effective in estimating the CCF contribution and risk insights of reference plant. This method will be a common bases for the optimization of new design for the construction plants as well as for the updating of safety assessment on the operating nuclear power plants.

• IE interfaces
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• v.25 no.4
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• pp.405-415
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• 2012

The reliability performance measures for low and high or continuous demand modes of operation of safety instrumented systems(SISs) are examined and compared by analyzing the official definitions in IEC 61508 standard. This paper also presents a status of common cause factor(CCF) models used in IEC 61508 and problems relating CCF modelling are discussed and ideas to solve these ones are suggested. An example with mixed M-out-of-N architecture is carried out to illustrate the proposed methods.

• IE interfaces
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• v.25 no.4
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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.

• Journal of Korean Medical classics
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• v.18 no.3 s.30
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• pp.126-135
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• 2005

통과분석(通過分析)${\ulcorner}$금궤요약심전${\lrcorner}$경병조문중우재경적주석(痙病條文中尤在痙的註釋), 득출여하결론(得出如下結論) 1. 경병적원인유이(痙病的原因有二) : 외인시태양풍한중감한습(外因是太陽風寒重感寒濕); 내인시혈기음양적손상(內因是血氣陰陽的損傷), 단진액부족시기공통지처(但津液不足是其共通之處). 2. 경병기본속우표병(痙病基本屬于表病), 출현심맥시인감수습사소치(出現沈脈是因感受濕邪所致). 3. 경병(痙病), 출현강직시인감수풍사(出現强直是因感受風邪). 4. 강경유오한증상(剛痙有惡寒症狀), 단유가능인위표실증무오한증상(但有可能認爲表實證無惡寒症狀), 고장원문중적'반'자직접인용과래설명(故將原文中的反字直接引用過來說明). 5. '기맥여고'화'폭복장대'시풍사거이습사잔존적시후출현적('其脈如故’和‘暴腹腸大'是風邪去而濕邪殘存存的時侯出現的). 6. 경병적양명어열증가사용대승기탕(痙病的陽明瘀熱證可使用大承氣湯), 기병불시위료거제조실(其幷不是爲了去除燥實), 이시위료하양명어열(而是爲了下陽明瘀熱), 고실제상사용대승기탕적시후요소심근신(故實際上使用大承氣湯的時候要小心謹愼).