• Title/Summary/Keyword: PRA

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A Comparison of Reliability Evaluation Tools for Power System Operation (전력계통 운영측면에서의 신뢰도 평가 Tool의 비교분석)

  • Choi, J.S.;Kwon, J.J.;Tran, T.T.;Jeon, D.H.;Park, Y.S.;Choi, H.S.;Yoon, Y.T.;Cha, J.M.
    • Proceedings of the KIEE Conference
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    • 2005.11b
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    • pp.198-200
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    • 2005
  • This paper illustrates the pragram features of reliability evaluation on operation mode (operational planning and operating) of power system. The eighty eight relative reports and papers with seventeen kinds of reliability programs were Investigated in this paper. Two programs, PRA and ASSESS, were focused on the operation mode reliability evaluation program and the comparions of the two program features are introduced.

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Development of Probabilistic Risk Analysis Model on Railroad System - Its Application to Tunnel Fire Risk Analysis (철도시스템의 확률론적 위험평가 모델 개발 연구 - 터널화재 위험도 평가에의 적용)

  • Kwak Sang Log;Wang Jong Bae;Hong Seon Ho;Kim Sang Am
    • Proceedings of the KSR Conference
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    • 2003.10b
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    • pp.265-270
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    • 2003
  • Though the probability of tunnel fire accident is very low, but critical fatalities are expected when it occurred. In this study the effect of critical safety parameters on tunnel fire accident are examined using probabilistic technique. Fire detection time, smoke spread velocity, passenger escape velocity, flash-over time, and emergency service arrival time are considered. In order to estimate the uncertainties of input parameters Monte Carlo simulation are used, and fatalities for each assumed accident scenarios are obtained as results. For the efficiency of iterative calculation PRA(Probabilistic Risk Analysis) code is developed in this study. As a result fire detection have large effect.

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Reliability Analysis of the Reactor Protection System Using Markov Processes (마코프 프로세스를 이용한 원자로 보호계통의 신뢰도 분석)

  • Jo, Nam-Jin
    • Nuclear Engineering and Technology
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    • v.19 no.4
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    • pp.279-291
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    • 1987
  • The event tree/fault tree techniques used in the current probabilistic risk assessment (PRA) of nuclear power plants are based on the binary and static description of the components and the system. While these techniques Bay be adequate in most of the safety studies, more advanced techniques, e.g., the Markov reliability analysis, are required to accurately study such problems as the plant availability assessments and technical specifications evaluations that are becoming increasingly important. This paper describes a Markov model for the Reactor Protection System of a pressurized water reactor and presents results of model evaluations for two testing policies in technical specifications.

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Identification and Analysis of External Event Combinations for Hanhikivi 1 PRA

  • Helander, Juho
    • Nuclear Engineering and Technology
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    • v.49 no.2
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    • pp.380-386
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    • 2017
  • Fennovoima's nuclear power plant, Hanhikivi 1, $Pyh{\ddot{a}}joki$, Finland, is currently in design phase, and its construction is scheduled to begin in 2018 and electricity production in 2024. The objective of this paper is to produce a preliminary list of safety-significant external event combinations including preliminary probability estimates, to be used in the probabilistic risk assessment of Hanhikivi 1 plant. Starting from the list of relevant single events, the relevant event combinations are identified based on seasonal variation, preconditions related to different events, and dependencies (fundamental and cascade type) between events. Using this method yields 30 relevant event combinations of two events for the Hanhikivi site. The preliminary probability of each combination is evaluated, and event combinations with extremely low probability are excluded from further analysis. Event combinations of three or more events are identified by adding possible events to the remaining combinations of two events. Finally, 10 relevant combinations of two events and three relevant combinations of three events remain. The results shall be considered preliminary and will be updated after evaluating more detailed effects of different events on plant safety.

Safety Analysis on the Tritium Release Accidents

  • Yang, Hee joong
    • Journal of Korean Society for Quality Management
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    • v.19 no.2
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    • pp.96-107
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    • 1991
  • At the design stage of a plant, the plausible causes and pathways of release of hazardous materials are not clearly known. Thus there exist large amount of uncertainties on the consequences resulting from the operation of a fusion plant. In order to better handle such uncertain circumstances, we utilize the Probabilistic Risk Assessment(PRA) for the safety analyses on fusion power plant. In this paper, we concentrate on the tritium release accident. We develop a simple model that describes the process and flow of tritium, by which we figure out the locations of tritium inventory and their vulnerability. We construct event tree models that lead to various levels of tritium release from abnormal initiating events. Branch parameters on the event tree are assessed from the fault tree analysis. Based on the event tree models we construct influence diagram models which are more useful for the parameter updating and analysis. We briefly discuss the parameter updating scheme, and finally develop the methodology to obtain the predictive distribution of consequences resulting from the operating a fusion power plant. We also discuss the way to utilize the results of testing on sub-systems to reduce the uncertain ties on over all system.

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Quantitative Hazard Analysis of Information Systems Using Probabilistic Risk Analysis Method

  • Lee, Young-Jai;Kim, Tae-Ho
    • Journal of Information Technology Applications and Management
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    • v.16 no.3
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    • pp.59-71
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    • 2009
  • Hazard analysis identifies probability to hazard occurrence and its potential impact on business processes operated in organizations. This paper illustrates a quantitative approach of hazard analysis of information systems by measuring the degree of hazard to information systems using probabilistic risk analysis and activity based costing technique. Specifically the research model projects probability of occurrence by PRA and economic loss by ABC under each identified hazard. To verify the model, each computerized subsystem which is called a business process and hazards occurred on information systems are gathered through one private organization. The loss impact of a hazard occurrence is produced by multiplying probability by the economic loss.

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Marine Casuality Forecasting System Based on the Virtual Reality Modeling Techniques(1) : Implementation Methodology (가상현실 모델링 기법을 적용한 해양안전사고 예보시스템 개발에 관한 연구(1) : 개발개념)

  • 임정빈
    • Proceedings of KOSOMES biannual meeting
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    • 2002.10a
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    • pp.163-175
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    • 2002
  • 가상현실 기법(virtual reality technologies)를 해양안전사고 가시화 시스템 개발에 적용하기 위한 개발론에 대해서 기술하였다. ‘목포해심’ 재결서 700여가지 사건에 대한 분류표와 수령화 표를 작성하여 질적 데이터를 양적 데이터로 변환하였다. 개발론에 대한 검토결과, 과거 10년 간의 해양사고 사건사례를 압축하여 저차원 데이터를 획득하기 위해서는 다변량해석기법(multivariate analysis)을 적용해야하고, 위기관리를 종합적으로 수행하기 위해서는 기존에 제시되고 있는 PRA, QRA, SPE 등의 기법 중 적합한 것을 적용할 필요가 있으며, 통계 데이터의 가시화를 위해서는 MATLAB의 Simulink 와 VR Toolkit을 이용하면 가능함을 분석할 수 있었다.

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A Study on Look alike Offender Detection Using Hidden Face Information (얼굴가림 정보를 이용한 유사 범인 검출에 관한 연구)

  • Kim, Soo-In
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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    • v.28 no.4
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    • pp.70-79
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    • 2014
  • In this paper, I propose a method for detection of look-alike offenders by using hidden face information. For extraction of moving objects, PRA matching is used to extract moving components, and brightness changes can be dealt with by an adaptive threshold adjusting in the proposed method. Moving objects extracted in the territory of the face region is extracted using the complexion, facial area, eyes, nose, mouth. The extracted information detected by the presence of these characteristics were likely to help judge a person. Results of the extracted face makes the recognition rate of possible murderers 90% so the usefulness of the proposed method was confirmed.

Effect of MDOF structures' optimal dampers on seismic fragility of piping

  • Jung, Woo Young;Ju, Bu Seog
    • Earthquakes and Structures
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    • v.9 no.3
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    • pp.563-576
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    • 2015
  • Over the past few decades, seismic retrofitting of structural systems has been significantly improved by the adoption of various methods such as FRP composite wraps, base isolation systems, and passive/active damper control systems. In parallel with this trend, probabilistic risk assessment (PRA) for structural and nonstructural components has become necessary for risk mitigation and the achievement of reliable designs in performance-based earthquake engineering. The primary objective of the present study was to evaluate the effect on piping fragility at T-joints due to seismic retrofitting of structural systems with passive energy-dissipation devices (i.e., linear viscous dampers). Three mid-rise building types were considered: without any seismic retrofitting; with distributed damper systems; with optimal placement of dampers. The results showed that the probability of piping system failure was considerably reduced in a Multi Degree of Freedom (MDOF) building retrofitted with optimal passive damper systems at lower floor levels. This effect of damper systems on piping fragility became insignificant as the floor level increased.

Probabilistic Risk Assessment Techniques for the Risk Analysis of Construction Projects (건설공사의 위험도분석을 위한 확률적 위험도 평가)

  • 조효남;임종권;박영빈
    • Proceedings of the Computational Structural Engineering Institute Conference
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    • 1997.04a
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    • pp.27-34
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    • 1997
  • In this paper, systematic and comprehensive approaches are suggested for the application of quantitative PRA techniques especially for those risk events that cannot be easily evaluated quantitatively In addition, dominant risk events are identified based on their occurrence frequency assessed by both actual survey of construction site conditions and the statistical data related with the probable accidents. Practical FTA(Fault Tree Analysis) and ETA(Event Tree Analysis) models are used for the assessment of the identified risks. When the risk events are lack of statistical data, appropriate Bayesian models incorporating engineering judgement and test results are also introduced in this paper. Moreover, a fuzzy probability technique is used for the quantitative risk assessment of those risk components which are difficult to evaluate quantitatively.

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