• 한국지진공학회논문집
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• 제13권2호
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• pp.47-58
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• 2009

본 연구에서는 변전소 시스템의 지진취약도 분석을 수행하여 변전소에 대한 지진취약도 함수를 제시하였다. 변전소는 여러 개의 설비와 구조물이 복합적으로 구성되어 있는 시스템이므로 각 설비에 대한 지진취약도 분석을 수행하여 이를 바탕으로 고장수목을 작성하여 변전소 전체의 파괴확률을 산정함으로써 변전소에 대한 지진취약도 평가를 수행하였다. 이를 위하여 국내 변전소의 현황을 파악하여 지진피해추정을 위한 변전소의 분류형식을 결정하였으며, 결정된 대표변전소 형식에 대한 평가대상 기기를 선정하였다. 대표 변전소 형식으로는 765kV, 345kV, 154kV 변전소의 GIS형 변전소로 결정하였다. 각 변전소의 취약도 검토대상 기기로는 변압기와 절연 애자를 선택하였다. 각 변전소의 변압기와 절연애자의 파괴모드와 파괴기준을 설정하여 지진취약도 곡선을 도출하였다. 최종적으로 변전소에 대한 고장수목을 이용하여 각 기기의 지진취약도 곡선으로부터 변전소 전체의 파괴확률을 산정하여 정의된 손상상태별 변전소의 지진취약도 함수를 산정하였다.

• 한국철도학회논문집
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• 제12권6호
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• pp.936-943
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• 2009

본 연구에서는 철도사고 위험분석 및 위험도 평가절차에 따라 철도건널목사고에 대한 정량적인 위험도평가를 위한 모델을 사건수목 및 고장수목 분석기법을 이용하여 개발하였다. 위험사건이 발생하여 인명피해로 결과하는 과정에서의 영향인자들을 분석하여 사고진전 시나리오를 구성하였으며, 고장수목분석(FTA, Fault Tree Analysis)을 이용하여 시나리오 경로별 발생확률을 산정하고, 사건수목분석(ETA, Event Tree Analysis)을 이용하여 심각도 값을 산정함으로써 이들의 조합으로 위험도를 산정하는 위험도 평가 모델을 제시하였다. 또한 실제발생한 위험도값과 개발모델을 이용하여 산정된 위험도값의 비교를 통하여 개발모델의 신뢰성 및 타당성을 검증하였다.

• 산업공학
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• 제22권2호
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• pp.126-134
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• 2009

As product quality and yield are essential factors in semiconductor manufacturing, monitoring the main manufacturing steps is a critical task. For the purpose, FDC(Fault detection and classification) is used for diagnosing fault states in the processes by monitoring data stream collected by equipment sensors. This paper proposes an FDC model based on decision tree which provides if-then classification rules for causal analysis of the processing results. Unlike previous decision tree approaches, we reflect the structural aspect of the data stream to FDC. For this, we segment the data stream into multiple subregions, define structural features for each subregion, and select the features which have high relevance to results of the process and low redundancy to other features. As the result, we can construct simple, but highly accurate FDC model. Experiments using the data stream collected from etching process show that the proposed method is able to classify normal/abnormal states with high accuracy.

• 한국안전학회지
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• 제32권1호
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• pp.41-46
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• 2017

In this paper, from making an electrical fire which is thought to be the most damaging among potential dangers as a top event, minimal cut sets (MCS) about it were analyzed. For this, components of a power substation were classified into 15 items. Failure rates and modes were extracted based on Korea Electrical Safety Corporation, IEEE Gold Book, and RAC. To analyze the top event (an electrical fire), main events were assorted into "safety devices for overcurrent" and "ampere meter of detecter". Failure of components was divided into failure of VCB, COS, and MCCB. A fault tree was composed of 3 AND gate, 5 OR gates and 17 basic events. Overlapped events among the basic events are things which occur from relevant components. They were attached to the tree by distinguishing identifiers. In case of FT, two minimal cut sets of "IO_METER", "MF_METER", "DO_MCCB" and "IO_METER", "MF_METER", "DO_VCB" take 46% of electrical fires. Therefore, about basic events which are included in the top two minimum cut sets, strict control is necessary.

• 전기저널
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• 4호통권100호
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• pp.48-51
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• 1985

• 한국화재소방학회논문지
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• 제30권4호
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• pp.73-81
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• 2016

정온전선은 평형 도체 사이에 반도전성 폴리머를 연속 압출 방식으로 충전시킨 후 양 도체 사이에 전기를 흐르게 함으로써 고분자에 의한 전열을 이용한 전기 발열체이다. 정온전선은 가격이 저렴하고 시공이 편리하기 때문에 겨울철 수배관의 동파방지용 열선으로 주로 사용되고 있다. 하지만 이러한 유용함에도 불구하고 구조적인 문제로 인하여 두 평형 도체의 절연이 파괴되는 경우에는 화재로 이어질 수도 있는 위험성이 존재하고 있다. 본 논문은 정온전선에 의한 화재현장을 조사하여 원인을 도출하는 방식으로 직접적인 원인을 추론하고자 하였으며, 결함수 분석을 통해 근본적인 문제를 파악해 보고자 하였다. 실제 냉동창고 화재현장을 조사하여 정온전선에 의한 화재원인을 추론한 결과 전선 말단 절연처리 결함에 의한 절연파괴인 것으로 판단되었다. 향후 이 결과는 안전활동 및 유사 화재원인조사 시에도 활용될 수 있을 것이다

• 제어로봇시스템학회논문지
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• 제19권4호
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• pp.328-333
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• 2013

Since a slight malfunction of control systems in a nuclear power plant may cause huge catastrophes, such control systems usually have multiple redundancy and reliable features, and their reliability and availability should be analyzed and verified thoroughly. This paper performed the reliability analysis of the SPLC (Safety Programmable Logic Controller) that is under developed as the control systems for the next generation nuclear power plant. One of the key features of SPLC is that it has multiple redundancy modes as faults happen, which means the reliability analysis for one fixed redundant model is not enough to analyze the reliability of SPLC. With considering this reconfigurable concept, FTA (Fault Tree Analysis) was used to capture fault-relationship among sub-modules. The analysis results show that MTTF (Mean Time to Fault) of SPLC is 45,080 hours, which is a about 4.5 times longer than the regulation, 10,000 hours.

• 한국안전학회지
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• 제12권3호
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• pp.155-160
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• 1997

The conventional fault tree and reliability analysis gives in many cases insufficient information concerning the relative frequencies of hazard events. This stems from that the basic events are not stationary and ergodic, and therefore the tolerances of the induced and top events cannot be calculated reliably based on the classical probability theory. To overcome this difficulty, the paper considers the relative frequencies of the basic events as fuzzy numbers and uses instead of probability, possible considerations for evaluating the mean values and tolerances of the top events. The possibility distribution of the basic events can be approximated based on heuristic considerations. This paper shows the use of these operators for constructing fault trees. The use of the method for numerical calculation is demonstrated on a field safety problem.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4560-4570
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• 2022

Dynamic fault tree (DFT) and its related research methods have received extensive attention in safety analysis and reliability engineering. DFT can perform reliability modelling for systems with sequential correlation, resource sharing, and cold and hot spare parts. A technical modelling method of DFT is proposed for modelling ship collision accidents and loss-of-coolant accidents (LOCAs). Qualitative and quantitative analyses of DFT were carried out using the cutting sequence (CS)/extended cutting sequence (ECS) method. The results show nine types of dynamic fault failure modes in ship collision accidents, describing the fault propagation process of a dynamic system and reflect the dynamic changes of the entire accident system. The probability of a ship collision accident is 2.378 × 10^-9 by using CS. This failure mode cannot be expressed by a combination of basic events within the same event frame after an LOCA occurs in a marine nuclear reactor because the system contains warm spare parts. Therefore, the probability of losing reactor control was calculated as 8.125 × 10^-6 using the ECS. Compared with CS, ECS is more efficient considering expression and processing capabilities, and has a significant advantage considering cost.

• Nuclear Engineering and Technology
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• 제39권2호
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• pp.123-128
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• 2007

In order to apply a static fault-tree (FT) method to a system or a plant whose configuration changes dynamically, condition gates and a post processing method are used to effectively accommodate these changes. An operator's performance change, which can be caused by these configuration changes, should also be considered to assess the risk to a plant in a more realistic manner. This study aims to develop an integrated framework to accommodate various configuration changes and their effect on an operator’s performance by using the FT model. We applied a condition-based human reliability assessment (CBHRA) method to consider various conditions endured by an operator. That is, we integrated the CBHRA method with the conventional post processing method for modeling the system configuration changes. The effect of the condition monitoring systems installed in a plant is also considered. In this study, we show an example application of the integrated framework to a probabilistic safety assessment for the shutdown phase of a nuclear power plant.