• 제목/요약/키워드: Fault tree analysis

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LPG충전소 안전장치의 사고방지 효과에 대한 정량적 분석 (Availability Analysis of Safety Devices installed for Preventing Accidental Event in the LPG Refuelling Station)

  • 이진한;유광수;박교식
    • 한국가스학회지
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    • 제10권1호
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    • pp.26-31
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    • 2006
  • LPG충전시설에 설치된 각종 안전장치의 유효성을 평가하기 위해 하역작업 중 탱크로리의 비등액체팽창증기폭발(BLEVE, Boiling Liquid Expanding Vapor Explosion) 시나리오에 대해 빈도분석을 수행하였으며, 분석방법으로는 정량적인 분석법인 결함수목분석(Fault Tree Analysis)법을 사용하였다. 안전장치의 유효성은 안전장치의 부착여부와 용량변화에 따른 빈도변화를 관찰함으로써 간접적으로 평가하였다. 이 분석을 통해 허용 가능한 위험수준을 만족하기 위해 필수적인 안전장치와 설치 우선순위를 도출할 수 있었다.

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양방향 컨버터의 커패시터 위치에 따른 고장률 분석 (Analysis of failure rate according to capacitor position of bidirectional converter)

  • 김예린;강필순
    • 전기전자학회논문지
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    • 제23권1호
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    • pp.261-265
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    • 2019
  • 기존 양방향 컨버터와 출력 커패시터를 추진용 배터리 쪽으로 이동시킨 양방향 컨버터의 고장률 변화를 분석한다. 두 컨버터의 회로 구조적 동일성과 차이점을 분석하여 커패시터 위치 변경으로 동작전압이 저감됨을 확인한다. 전압스트레스 인자와 동작온도에 따른 커패시터 부품 고장률을 구하고 양방향 컨버터의 고장나무에 적용하여 컨버터 전체 고장률을 구한다. 동작온도와 커패시턴스 값에 따른 고장률과 평균고장시간을 비교 분석하여 설계 변경으로 인한 장 단점을 분석한다.

인간신뢰도분석에서의 인간행위 의존성 평가: 암모니아 저장시설의 누출사고 평가 예

  • 강대일;이윤환;진영호
    • 한국산업안전학회:학술대회논문집
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    • 한국안전학회 1998년도 추계 학술논문발표회 논문집
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    • pp.219-224
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    • 1998
  • 확률론적 안전성 평가(Probabilistic Safety Assessment PSA)나 정량적인 위험도 평가(Quantitative Risk Assessment: QRA)에서 인간신뢰도분석(human reliability analysis)은 인간행위를 기기처럼 생각하여 전체 시스템의 안전성에 중요한 초기사건(initiating event) 이전이나 초기사건 이후 또는 초기사건을 유발하는 인간행위를 파악하고 정량화하여, 확률론적 평가의 논리구조인 사건 및 고장수목(event tree 및 fault tree)이나 사고경위 단절집합 (accident sequence outsets)에 포함시키는 것이다. (중략)

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산업시설의 사고빈도분석을 위한 Easy-Tree 개발

  • 임동연;고재욱;김윤화;서재민
    • 한국산업안전학회:학술대회논문집
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    • 한국안전학회 1999년도 춘계 학술논문발표회 논문집
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    • pp.121-124
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    • 1999
  • 항공 산업분야의 사고빈도분석을 위해 개발된 이상트리분석(Fault Tree Analysis) 방법은 최근 들어 넓은 분야에 거쳐 광범위하게 사용되고 있다. 특히 화학공장의 위험성을 평가하는 방법 중 크게 각광받고 있는 정량적 위험성평가의 사고의 빈도를 분석하는 방법으로 그 중요성이 증가되고 있다. 하지만 아직까지 국내 현실은 인식과 데이터의 부족으로 업체 스스로가 시설물의 안전가동을 위해 이러한 분석방법을 수행하기에는 상당히 어려운 점이 많은 실정이다. (중략)

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A Quantitative Study on Important Factors of the PSA of Safety-Critical Digital Systems

  • Kang, Hyun-Gook;Taeyong Sung
    • Nuclear Engineering and Technology
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    • 제33권6호
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    • pp.596-604
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    • 2001
  • This paper quantitatively presents the effects of important factors of the probabilistic safety assessment (PSA) of safety-critical digital systems. The result which is quantified using fault tree analysis methodology shows that these factors remarkably affect the system safety. In this paper we list the factors which should be represented by the model for PSA. Based on the PSA experience, we select three important factors which are expected to dominate the system unavailability. They are the avoidance of common cause failure, the coverage of fault tolerant mechanisms and software failure probability. We Quantitatively demonstrate the effect of these three factors. The broader usage of digital equipment in nuclear power plants gives rise to the safety problems. Even though conventional PSA methods are immature for applying to microprocessor-based digital systems, practical needs force us to apply it because the result of PSA plays an important role in proving the safety of a designed system. We expect the analysis result to provide valuable feedback to the designers of digital safety- critical systems.

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Off-Site 패키지형 수소충전소의 FTA 분석 (A Study on FTA of Off-Site Packaged Hydrogen Station)

  • 서두현;김태훈;이광원;최영은
    • 한국수소및신에너지학회논문집
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    • 제31권1호
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    • pp.73-81
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    • 2020
  • For the fault tree analysis (FTA) analysis of the packaged hydrogen filling station, the composition of the charging station was analyzed and the fault tree (FT) diagram was prepared. FT diagrams were created by dividing the causes of events into external factors and internal factors with the hydrogen event as the top event. The external factors include the effects of major disasters caused by natural disasters and external factors as OR gates. Internal factors are divided into tube tailer, compressor & storage tank, and dispenser, which are composed of mistakes in operation process and causes of accidents caused by parts leakage. In this study, the purpose was to improve the hydrogen station. The subjects of this study were domestic packaged hydrogen stations and FTA study was conducted based on the previous studies, failure mode & effect analysis (FMEA) and hazard & operability study (HAZOP). Top event as a hydrogen leaking event and constructed the flow of events based on the previous study. Refer to "Off shore and onshore reliability data 6th edition", "European Industry Reliability Data Bank", technique for human error rate prediction (THERP) for reliability data. We hope that this study will help to improve the safety and activation of the hydrogen station.

서비스 블루프린트와 FTA를 이용한 서비스 신뢰도 평가모델 (Evaluation Model of Service Reliability Using a Service Blueprint and FTA)

  • 유정상;오형술
    • 산업경영시스템학회지
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    • 제35권4호
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    • pp.194-201
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    • 2012
  • Because the difference between products and services are getting less and less, service and manufacturing companies' efforts are increasingly focused on utilizing services to satisfy customers' needs under today's competitive market environment. The value of services depends on service reliability that is identified by satisfaction derived from the relationship between customer needs and service providers. In this paper, we extend concepts from the fault tree analysis for reliability analysis of tangible systems to services. We use an event-based process model to facilitate service design and represent the relationships between functions and failures in a service. The objective of this research is to propose a method for evaluating service reliability based on service processes using service blueprint and FTA. We can identify the failure mode of service in a service delivery process with a service blueprint. The fuzzy membership function is used to characterize the probability of failure based on linguistic terms. FTA is employed to estimate the reliability of service delivery processes with risk factors that are represented as potential failure causes. To demonstrate implementation of the proposed method, we use a case study involving a typical automotive service operation.

교량구조시스템의 유지관리를 위한 퍼지 신뢰성해석 모델 (Fuzzy Reliability Analysis Models for Maintenance of Bridge Structure Systems)

  • 김종길;손용우;이증빈;이채규;안영기
    • 한국전산구조공학회:학술대회논문집
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    • 한국전산구조공학회 2003년도 가을 학술발표회 논문집
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    • pp.103-114
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    • 2003
  • This paper aims to propose a method that helps maintenance engineers to evaluate the damage states of bridge structure systems by using a Fuzzy Fault Tree Analysis. It may be stated that Fuzzy Fault Tree Analysis may be very useful for the systematic and rational fuzzy reliability assessment for real bridge structure systems problems because the approach is able to effectively deal with all the related bridge structural element damages in terms of the linguistic variables that incorporate systematically experts experiences and subjective judgement. This paper considers these uncertainties by providing a fuzzy reliability-based framework and shows that the identification of the optimum maintenance scenario is a straightforward process. This is achieved by using a computer program for LIFETIME. This program can consider the effects of various types of actions on the fuzzy reliability index profile of a deteriorating structures. Only the effect of maintenance interventions is considered in this study. However. any environmental or mechanical action affecting the fuzzy reliability index profile can be considered in LIFETIME. Numerical examples of deteriorating bridges are presented to illustrate the capability of the proposed approach. Further development and implementation of this approach are recommended for future research.

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A decision support system (DSS) for construction risk efficiency in Taiwan

  • Tsai, Tsung-Chieh;Li, Hsiang-Wen
    • Smart Structures and Systems
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    • 제21권2호
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    • pp.249-255
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    • 2018
  • Many studies in risk management have been focused on management process, contract relation, and risk analysis in the past decade, but very few studies have addressed project risks from the perspective of risk efficiency. This study started with using Fault Tree Analysis to develop a framework for the decision-making support system of risk management from the perspective of risk efficiency, in order for the support system to find risk strategies of optimal combination for the project manager by the trade-off between project risk and cost of project strategies. Comprehensive and realistic risk strategies must strive for optimal decisions that minimize project risks and risk strategies cost while addressing important data such as risk causes, risk probability, risk impact and risk strategies cost. The risk management in the construction phase of building projects in Taiwan upon important data has been analyzed, that provided the data for support system to include 247 risk causes. Then, 17 risk causes were extracted to demonstrates the decision-making support system of risk management from the perspective of risk efficiency in building project of Taiwan which could reach better combination type of risk strategies for the project manager by the trade-off between risk cost and project risk.

Level 1 probabilistic safety assessment of supercritical-CO2-cooled micro modular reactor in conceptual design phase

  • So, Eunseo;Kim, Man Cheol
    • Nuclear Engineering and Technology
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    • 제53권2호
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    • pp.498-508
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    • 2021
  • Micro reactors are increasingly being considered for utilization as distributed power sources. Hence, the probabilistic safety assessment (PSA) of a direct supercritical-CO2-cooled fast reactor, called micro modular reactor (MMR), was performed in this study; this reactor was developed using innovative design concepts. It adopted a modular design and passive safety systems to minimize site constraints. As the MMR is in its conceptual design phase, design weaknesses and valuable safety insights could be identified during PSA. Level 1 internal event PSA was carried out involving literature survey, system characterization, identification of initiating events, transient analyses, development of event trees and fault trees, and quantification. The initiating events and scenarios significantly contributing to core damage frequency (CDF) were determined to identify design weaknesses in MMR. The most significant initiating event category contributing to CDF was the transients with the power conversion system initially available category, owing to its relatively high occurrence frequency. Further, an importance analysis revealed that the safety of MMR can be significantly improved by improving the reliability of reactor trip and passive decay heat removal system operation. The findings presented in this paper are expected to contribute toward future applications of PSA for assessing unconventional nuclear reactors in their conceptual design phases.