• Journal of KIISE:Software and Applications
• /
• v.32 no.12
• /
• pp.1178-1191
• /
• 2005

In this paper, we propose a synthesis method of software fault tree from software requirements specification written in NuSCR formal specification language. The software fault tree, proposed in this paper, reflects requirements on both structure and behavior and it is an integrated form. The software fault tree can be used for analyzing safety in the view of structure and behavior. We propose templates for each components in NuSCR specification language and a synthesis method of software fault tree using the templates. The research was applied into the main trip logic of the reactor protection system of ARP1400, the Korean next generation nuclear reactor system, developed by KNICS. And we evaluate feasibility of our approach through this case study.

• Nuclear Engineering and Technology
• /
• v.16 no.2
• /
• pp.97-105
• /
• 1984

A method and computer code for the uncertainty analysis in the top event unavailability are developed and tested by combining Monte Carlo Method and Moments method with fault tree reduction technique. Using system fault trees and unavailability data selected in WASH-1400, the efficiency of the proposed method is tested and these results are compared with those obtained by Monte Carlo method. It is shown that the results are sufficiently good in accuracy and computation time is considerably reduced compared with those by Monte Carlo method.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05b
• /
• pp.610-615
• /
• 1996

PSA 모델링 및 데이타 관리를 효과적으로 수행하고 PSA 정량화를 자동화할 수 있도록 PSA workstation 을 개발하고 있다. Windows용 고장수목 및 사건수목 편집기, 데이타 관리 모듈 개발등의 PSA모델링 및 관리 모듈이 개발되었고, 또한 최소단절집합 생성 방법 개선, 규칙기반 회복조치 분석 및 고장수목 순환논리 분석 방법 개발등을 통한 PSA 정량화 방법의 개선이 이루어졌다. PSA workstation은 PSA 응용 소프트웨어 개발의 기초로도 사용될 수 있다.

• Journal of the Korean Society for Railway
• /
• v.12 no.6
• /
• pp.936-943
• /
• 2009

In this study, a risk assessment model based on the ETA (Event Tree Analysis) and FTA (Fault Tree Analysis) is developed according to the procedure of hazard analysis and risk assessment in order to estimate the risk quantitatively. The FTA technique is applied to estimate the branch probability (frequency) and the ETA technique is applied to estimate the consequence for each branch path on the ET (Event Tree). A risk assessment model is developed by the combination of those ETA and FTA. In addition, the reliability and the validity of the risk assessment model are verified by comparing the risk estimated through the developed model with the actual equivalent fatality.

• Proceedings of the Korean Institute of Industrial Safety Conference
• /
• 1997.11a
• /
• pp.179-184
• /
• 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)

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05b
• /
• pp.570-575
• /
• 1996

1단계 확률론적 안전성 평가 (Level 1 Probabilistic Safety Assessment, PSA)를 수행할 때 나타나는 보조계통 고장 수목간의 순환 논리는 사고 경위 정량화를 위하여 해결되어야만 한다. 기존의 PSA에서는 이를 위하여 별도의 고장 수목을 다시 작성하였으나, 이 방법을 사용하기 위하여서는 보조계통 간의 관계를 검토하여야 하며, 이에 따른 별도의 고장 수목을 작성하여야 하는 등 추가적인 작업이 요구된다. 또한 기존 방법은 일부 최소 단절군이 생성되지 않는 약점을 갖고 있다. 이에 따라 한국원자력연구소에서는 해석적으로 순환 논리를 푸는 방법을 개발하였으며, 이를 PSA용 코드인 KIRAP 코드에 구축하였다. 이에 따라 기존 방법의 약점을 극복하고 고장 수목간의 순환 논리를 자동으로 풀 수 있게 되었다. 본 논문에서는 개발된 해석적 방법을 설명하며, 또한 이 방법을 실제 PSA에 적용하며 나타난 여러 현상에 대하여 살펴본다.

• Proceedings of the Korean Institute of Industrial Safety Conference
• /
• 2003.05a
• /
• pp.114-119
• /
• 2003

원자력발전소를 비롯한 위험 시설물의 확률론적 안전성 평가(Probabilistic Safety Assessment: PSA)는 고장수목(Fault Tree) 및 사건수목(Event Tree) 분석으로 이루어지며, 분석 결과로 그 시설물의 위험도(Risk)는 최소단절집합(Minimal Cutsets)들의 합으로 구성 된다.(중략)

• Journal of the Korean Society for Railway
• /
• v.11 no.6
• /
• pp.530-535
• /
• 2008

After train fire accident in Daegue, many research on train fire safety improvement have been carrying out. Since many alternative fire safety measures can be applied in our railway system, the effect of the each safety measure must be quantified prior to the safety investment. In order to estimate the effects of each safety measure quantitatively, fault trees and event trees are constructed in this study. Results can be applied for cost-benefit analysis or sensitivity analysis for safety measures in risk assessment process.

• Proceedings of the KSR Conference
• /
• 2007.05a
• /
• pp.605-613
• /
• 2007

In order to overcome the difficulties of quantitative risk analysis such as complexity of model, we propose a systematic methodology for risk quantification of railway system which consists of 6 steps: The identification of risk factors, the determination of major scenarios for each risk factor by using event tree, the development of supplementary fault trees for evaluating branch probabilities, the evaluation of event probabilities, the quantification of risk, and the analysis in consideration of accident situation. In this study, in order to address the feasibility of the propose methodology, this framework is applied to the prototype risk model of nation-wide railway level crossings. And the quantification result based on the data of 2005 in Korea will also be presented.

• Journal of the Earthquake Engineering Society of Korea
• /
• v.13 no.2
• /
• pp.47-58
• /
• 2009

In this study, a seismic fragility analysis was performed for substation systems in Korea. To evaluate the seismic fragility function of the substation systems, a fragility analysis of the individual equipment and facilities of the substation systems was first performed, and then all systems were considered in the fragility analysis of the substation systems using a fault-tree method. For this research, the status of the substation systems in Korea was investigated for the classification of the substation systems. Following the classification of the substation systems, target equipment was selected based on previous damage records in earthquake hazards. The substation systems were classified as 765kV, 345kV, and 154kV systems. Transformer and bushing were chosen as target equipment. The failure modes and criteria for transformer and bushing were decided, and fragility analysis performed. Finally, the fragility functions of substation system were evaluated using the fault tree method according to damage status.