• 전기전자학회논문지
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• 제23권1호
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• pp.254-260
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• 2019

본 논문에서는 양방향 dc-to-dc 컨버터의 고장원인, 고장영향, 고장 결과를 파악하기 위한 failure mode and effect analysis(FMEA)와 양방향 컨버터의 위험도를 고려한 fault-tree analysis(FTA)를 통해 고장률을 예측한다. 전기차의 구동전압을 효율적으로 상승시키기 위해 인버터 앞단에 부착되는 양방향 컨버터는 배터리 전력을 dc-link 커패시터로 방전시키는 승압모드와 회생전력을 배터리로 충전시키는 강압모드를 가진다. 양방향 컨버터의 동작 특성을 고려한 FMEA 결과를 바탕으로 컨버터의 위험도를 고려한 고장나무를 설계한다. 전기차 MCU용에 맞는 설계 파라메타를 설정하고 출력전압 리플과 인덕터 전류 리플에 따른 커패시터와 인덕터의 부품 고장률을 분석한다. 또한 동작 온도에 따른 주요부품의 고장률을 MIL-HDBK-217F를 이용하여 구한다. 마지막으로 부품 고장률을 고장나무의 기본 사상의 고장률로 반영하여 컨버터 고장률과 평균고장시간을 예측한다.

• Nuclear Engineering and Technology
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• 제16권2호
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• pp.97-105
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• 1984

고장수목 정점사상에 대한 이용불능도의 불화실성을 분석하기 위한 방법 및 전산코드를 개발하였으며 그 유용성을 검증하였다. 이 방법은 몬테카를로 방법과 모멘트 방법을 고장수목 축소 기법과 함께 조합하여 개발하였고 WASH-1400에 있는 고장수목과 신뢰도 자료를 이용하여 본 연구에서 개발된 코드의 효율성을 검증하였다. 몬테카를로 방법과의 비교결과 이 방법을 이응하면 계산시간을 상당히 줄일 수 있으며 충분히 정확한 결과를 얻을 수 있음을 입증하였다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2000년도 추계학술대회 논문집 학회본부 D
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• pp.615-617
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• 2000

Temporal Logic Frameworks is convenient to represent temporal relation. It is useful to represent a dynamic properties of Discrete Event Dynamic Systems. Also, it is convenient to express a current and next state of event using logical representation. Because the teachability tree of the Temporal Logic Frameworks is very complexity it is difficult to understand. In this paper, we defined some rules to represent Temporal Logic Frameworks by Petri Net and proposed am method of the representation of them Petri Net for the Temporal Logic Frameworks. An example are used to demonstrate the feasibility of this method.

• 에너지공학
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• 제26권4호
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• pp.23-28
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• 2017

Hazard evaluation and FTA are performed as the first and the second step of QRA for a LNG storage tank. Hazards are identified using HAZOP. Each segment of the system is examined, and we list all possible deviations from normal operating conditions and how they might occur. The consequences on the process are assessed, and the means available to detect and correct the deviations are reviewed. The FTA is carried out to analyse the hazards identified from the HAZOP study. A top event is selected to be release of LNG. Then all combinations of individual failures that can lead to the hazardous event are shown in the logical format of the fault tree system.

• Nuclear Engineering and Technology
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• 제49권3호
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• pp.517-524
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• 2017

Cyber security is an important issue in the field of nuclear engineering because nuclear facilities use digital equipment and digital systems that can lead to serious hazards in the event of an accident. Regulatory agencies worldwide have announced guidelines for cyber security related to nuclear issues, including U.S. NRC Regulatory Guide 5.71. It is important to evaluate cyber security risk in accordance with these regulatory guides. In this study, we propose a cyber security risk evaluation model for nuclear instrumentation and control systems using a Bayesian network and event trees. As it is difficult to perform penetration tests on the systems, the evaluation model can inform research on cyber threats to cyber security systems for nuclear facilities through the use of prior and posterior information and backpropagation calculations. Furthermore, we suggest a methodology for the application of analytical results from the Bayesian network model to an event tree model, which is a probabilistic safety assessment method. The proposed method will provide insight into safety and cyber security risks.

• 한국압력기기공학회 논문집
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• 제14권2호
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• pp.49-58
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• 2018

The regulatory periodic inspection program (PSI) conducted at every overhaul period is the most important process for confirming the safety of nuclear power plants. The PSI for operating nuclear power plants in Korea mainly consist of component level performance check that had been developed based on deterministic approach putting the same degree of importance to all the inspection items. This inspection methodology is likely to be effective for preoperational inspection. However, once the plant is put into service, the PSI must be focused on whether to minimize the risk of accident using defense-in-depth concept and risk insight. The incorporation of defense-in-depth concept and risk insight into the deterministic based safety inspection has not been well studied so far. In this study, two track approaches are proposed to make sure that core damage be avoided: one is to secure success path and the other to block the failure path in a specific event tree of PSA. The investigation shows how to select safety important components and how to set up inspection group to ensure that core damage would not occur for a given initiating event, which results in strengthening defense-in-depth level 3.

• Nuclear Engineering and Technology
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• 제54권6호
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• pp.2084-2093
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• 2022

Probabilistic safety assessment is widely used to quantify the risks of nuclear power plants and their uncertainties. When the lognormal distribution describes the uncertainties of basic events, the uncertainty of the top event in a fault tree is approximated with the sum of lognormal random variables after minimal cutsets are obtained, and rare-event approximation is applied. As handling complicated analytic expressions for the sum of lognormal random variables is challenging, several approximation methods, especially Monte Carlo simulation, are widely used in practice for uncertainty analysis. In this study, a theoretical approach for analyzing the sum of lognormal random variables using an efficient numerical integration method is proposed for uncertainty analysis in probability safety assessments. The change of variables from correlated random variables with a complicated region of integration to independent random variables with a unit hypercube region of integration is applied to obtain an efficient numerical integration. The theoretical advantages of the proposed method over other approximation methods are shown through a benchmark problem. The proposed method provides an accurate and efficient approach to calculate the uncertainty of the top event in probabilistic safety assessment when the uncertainties of basic events are described with lognormal random variables.

• Nuclear Engineering and Technology
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• 제54권8호
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• pp.2933-2940
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• 2022

Approximations such as the delete-term approximation, rare event approximation, and minimal cutset upper bound (MCUB) need to be prudently applied for the quantification of a seismic probabilistic safety assessment (PSA) model. Important characteristics of seismic PSA models indicate that preserving the success branches in a primary seismic event tree is necessary. Based on the authors' experience in modeling and quantifying plant-level seismic PSA models, the effects of applying negate-down to the success branches in primary seismic event trees on the quantification results are summarized along with the following three insights gained: (1) there are two competing effects on the MCUB-based quantification results: one tending to increase and the other tending to decrease; (2) the binary decision diagram does not always provide exact quantification results; and (3) it is identified when the exact results will be obtained, and which combination provides more conservative results compared to the others. Complicated interactions occur in Boolean variable manipulation, approximation, and the quantification of a seismic PSA model. The insights presented herein can assist PSA analysts to better understand the important theoretical principles associated with the quantification of seismic PSA models.

• 예술인문사회 융합 멀티미디어 논문지
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• 제8권5호
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• pp.417-425
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• 2018

본 논문에서는 조선해양 작업장에서 발생하는 중대재해를 줄이고 체계적인 안전관리를 위하여 ETA(event tree analysis)기반 시나리오 도출 및 ICT 기술접목을 통한 안전관리 구축방안을 제안한다. 안전보건공단과 (구)국민안전처의 통계결과 조선해양 관련 중대재해 중 가장 많이 발생하는 사고유형은 떨어짐이고, 주요사고원인은 안전대 미착용 및 안전대 고리 미체결이다. 이 문제를 해결하기 위해 ETA기반의 시나리오를 작성하여 안전사항에 따른 결과를 도출하고 이 결과를 바탕으로 사고예방을 위한 ICT 기술접목으로 해결방안을 제시한다. ETA 기반 시나리오 도출 및 ICT 기술접목을 통해 제안한 해결방안으로는 안전대 및 안전모 착용여부 감지시스템, 안전대 고리 체결여부 감지시스템, 안전거리 측정을 위한 걸이설비 측정시스템이다. 안전사항별 시스템을 통해 작업자의 떨어짐 위험을 줄여 사망확률을 낮출 수 있다. 제안한 방안을 통해 사고를 예방함으로써 조선해양 분야의 중대재해를 줄이고 체계적인 안전관리를 도모한다.

• 한국산업안전학회:학술대회논문집
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• 한국안전학회 1997년도 추계 학술논문발표회 논문집
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• pp.179-184
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• 1997

지금까지 수행되었던 원자력발전소의 확률론적 안전성 평가 (Probabilistic Safety Assessment; PSA) 결과, 노심손상 빈도의 30% - 70%가 인간행위와 관련이 있는 것으로 밝혀져 PSA에서 인간행위를 적절히 다루는 것은 매우 중요하다. 특히 원자력발전소의 정지운전인 경우에는 자동으로 작동하는 계통이 거의 없어 고장수목(fault tree)과 사건수목(event tree)의 모델링에 많은 운전인 행위가 포함되기 때문에 노심손상 빈도와 관련이 있는 인간행위는 전출력 운전(full power operation)에 대한 PSA 결과의 경우보다 많은 것으로 나타났다. PSA에서 인간신뢰도분석(human reliability analysis)은 PSA의 논리구조인 고장수목과 사건수목에 모델링될 인간행위를 파악하고 정량화하는 것이다. 현재 인간신뢰도분석은 인간행위에 대한 데이타의 부족과 인간행위 자체의 다변성(variability)으로 인해 분석에 어려움이 있고 분석자의 주관성이 개입될 여지가 많은 실정이며, 이에 따라 분석 결과에는 많은 불확실성을 내포하게 된다. (중략)