• 제목/요약/키워드: Event tree

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Risk Analysis of Container Ship Accidents and Risk Mitigation Measures

  • Kim, Dong-Jin;Kwak, Su-Yong
    • 해양환경안전학회지
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    • 제22권3호
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    • pp.259-267
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    • 2016
  • The study performs a risk analysis on container ship accidents using accident data collected over the six years from 2006 to 2011, presents the resulting risk level, and suggests three risk mitigation measures to reduce the overall risk, for the safer operation of container ships. More specifically, starting from the initial accident of collision, we developed 13 different accident scenarios using event tree analysis based on which the overall risk level was obtained and presented as a FN curve. Since diverse human factors are the main cause of most of the ship accidents, our study focuses on the effect of reducing human causes on the resulting risk level. For the research we considered the injuries for the calculation of fatality with the help of MAIS. The results show that collision was the main type of accident, accounting for 62 % of all accidents, and the measures employed were proven to be effective in the sense that the risk level was much lowered and the average number of fatalities was also reduced. With more data accumulated, more precise risk level will be calculated with which the practical risk mitigating measures will be also developed. For future study, economic loss and environmental damage as consequences need to be considered.

Development of a Computer Code, CONPAS, for an Integrated Level 2 PSA

  • Ahn, Kwang-Il;Kim, See-Darl;Song, Yong-Mann;Jin, Young-Ho;Park, Chung K.
    • Nuclear Engineering and Technology
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    • 제30권1호
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    • pp.58-74
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    • 1998
  • A PC window-based computer code, CONPAS (CONtainment Performance Analysis System), has been developed to integrate the numerical, graphical, and results-operation aspects of Level 2 probabilistic safety assessments (PSA) for nuclear power plants automatically. As a main logic for accident progression analysis, it employs a concept of the small containment phenomenological event tree (CPET) helpful to trace out visually individual accident progressions and of the detailed supporting event tree (DSET) for its detailed quantification. For the integrated analysis of Level 2 PSA, the code utilizes five distinct, but closely related modules. Its computational feasibility to real PSAs has been assessed through an application to the UCN 3&4 full scope Level 2 PSA. Compared with other existing computer codes for Level 2 PSA, the CONPAS code provides several advanced features: (1) systematic uncertainty analysis / importance analysis / sensitivity analysis, (2) table / graphical display & print, (3) employment of the recent Level 2 PSA technologies, and (4) highly effective user interface. The main purpose of this paper is to introduce the key features of CONPAS code and results of its feasibility study.

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Application of Dynamic Probabilistic Safety Assessment Approach for Accident Sequence Precursor Analysis: Case Study for Steam Generator Tube Rupture

  • Lee, Hansul;Kim, Taewan;Heo, Gyunyoung
    • Nuclear Engineering and Technology
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    • 제49권2호
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    • pp.306-312
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    • 2017
  • The purpose of this research is to introduce the technical standard of accident sequence precursor (ASP) analysis, and to propose a case study using the dynamic-probabilistic safety assessment (D-PSA) approach. The D-PSA approach can aid in the determination of high-risk/low-frequency accident scenarios from all potential scenarios. It can also be used to investigate the dynamic interaction between the physical state and the actions of the operator in an accident situation for risk quantification. This approach lends significant potential for safety analysis. Furthermore, the D-PSA approach provides a more realistic risk assessment by minimizing assumptions used in the conventional PSA model so-called the static-PSA model, which are relatively static in comparison. We performed risk quantification of a steam generator tube rupture (SGTR) accident using the dynamic event tree (DET) methodology, which is the most widely used methodology in D-PSA. The risk quantification results of D-PSA and S-PSA are compared and evaluated. Suggestions and recommendations for using D-PSA are described in order to provide a technical perspective.

해군함정 화재 위험도 평가에 관한 연구 (A Study on Risk Assessment for Fire Onboard a Naval Vessel)

  • 전계룡;김동진
    • 한국화재소방학회논문지
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    • 제22권5호
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    • pp.35-42
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    • 2008
  • 최근 KDX-III, LPX 등 대형함 건조사업의 진행으로 예전과 달리 함정 규모가 커지고 함정 내 승조원수 및 승조 인원 구성도 다양화 되고 있는 상황을 반영하여 화재로 인한 해군함정의 위험도를 정량적으로 평가 분석하였다. 이를 위해 해군 함정의 복잡한 화재 전파양상을 사건수목분석(ETA)기법으로 모델링하였고, 승조원 침실 내 화재해석을 위해 CFAST 프로그램을 이용하여 화재 전파양상 및 화재구역 내거주가능시간(임계시간)을 예측하였다. 이를 승조원 탈출 시간과 비교하여 상황별 사망자 수를 산출하였으며 FN-curve로 전반적인 위험도를 도식하여 화재 위험도의 수용여부를 판단할 수 있는 방법을 제시하였다. 본 연구에서 제시된 방법론을 바탕으로 새롭게 건조되는 함정 설계단계에서 화재 발생시 함정에서의 인명위험성을 적절하게 평가할 수 있는 도구로 활용이 가능할 것으로 사료된다.

METHOD FOR THE ANALYSIS OF TEMPORAL CHANGE OF PHYSICAL STRUCTURE IN THE INSTRUMENTATION AND CONTROL LIFE-CYCLE

  • Goring, Markus;Fay, Alexander
    • Nuclear Engineering and Technology
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    • 제45권5호
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    • pp.653-664
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    • 2013
  • The design of computer-based instrumentation and control (I&C) systems is determined by the allocation of I&C functions to I&C systems and components. Due to the characteristics of computer-based technology, component failures can negatively affect several I&C functions, so that the reliability proof of the I&C systems requires the accomplishment of I&C system design analyses throughout the I&C life-cycle. On one hand, this paper proposes the restructuring of the sequential IEC 61513 I&C life-cycle according to the V-model, so as to adequately integrate the concept of verification and validation. On the other hand, based on a metamodel for the modeling of I&C systems, this paper introduces a method for the modeling and analysis of the effects with respect to the superposition of failure combinations and event sequences on the I&C system design, i.e. the temporal change of physical structure is analyzed. In the first step, the method is concerned with the modeling of the I&C systems. In the second step, the method considers the analysis of temporal change of physical structure, which integrates the concepts of the diversity and defense-in-depth analysis, fault tree analysis, event tree analysis, and failure mode and effects analysis.

수소 충전소에 대한 정량적 안전성 평가 (Quantitative Safety Assessment for Hydrogen Station)

  • 성대현;이광원;김태훈;오동석;오영달;서두현;김영규;김은정
    • 한국안전학회지
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    • 제27권3호
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    • pp.111-116
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    • 2012
  • This study is about the quantitative safety assessment of hydrogen station in Korea operating with on-site type. This was written by background information that before qualitative safety assessment to write. For the qualitative safety assessment method, the study used FMEA(failure mode & effect analysis) and HAZOP(hazard & operability), and adopted the FTA(fault tree analysis) as the quantitative safety assessment method. To write the FTA, we wrote FT by Top event that hydrogen leakage can be called most serious accident of hydrogen station. Each base event collect reliability data by reliability data handbook, THERP-HRA and estimation of the engineering. Assessment looked at the high frequency and the possible risk through Gate, Importance, m.cutsets analysis.

RISK-INFORMED REGULATION: HANDLING UNCERTAINTY FOR A RATIONAL MANAGEMENT OF SAFETY

  • Zio, Enrico
    • Nuclear Engineering and Technology
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    • 제40권5호
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    • pp.327-348
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    • 2008
  • A risk-informed regulatory approach implies that risk insights be used as supplement of deterministic information for safety decision-making purposes. In this view, the use of risk assessment techniques is expected to lead to improved safety and a more rational allocation of the limited resources available. On the other hand, it is recognized that uncertainties affect both the deterministic safety analyses and the risk assessments. In order for the risk-informed decision making process to be effective, the adequate representation and treatment of such uncertainties is mandatory. In this paper, the risk-informed regulatory framework is considered under the focus of the uncertainty issue. Traditionally, probability theory has provided the language and mathematics for the representation and treatment of uncertainty. More recently, other mathematical structures have been introduced. In particular, the Dempster-Shafer theory of evidence is here illustrated as a generalized framework encompassing probability theory and possibility theory. The special case of probability theory is only addressed as term of comparison, given that it is a well known subject. On the other hand, the special case of possibility theory is amply illustrated. An example of the combination of probability and possibility for treating the uncertainty in the parameters of an event tree is illustrated.

고속도로 교통안전시설물의 정성적 및 정량적 위험도분석 연구 (A Study of Qualitative and Quantitative Risk Assessment for Highway Safety Facilities)

  • 지동한;오영태;최현호
    • 한국건설관리학회논문집
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    • 제8권4호
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    • pp.99-109
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    • 2007
  • 교통시설물의 위험요소는 안전피해의 규모 및 종류 등 복잡한 제반요소에 영향을 받기 때문에 안전개념에 기초한 분석이 요구된다. 이를 위해 본 연구에서는 교통안전시설에 대한 정성적 및 정량적 위험도분석 방법을 제시하고 이를 가치평가에 도입할 수 있는 절차를 제안하였다. 또한 정량적 분석을 위해 교통사고 데이터 및 이를 분석한 EPDO(Equivalent Property Damage Only)를 이용하여 사고빈도와 피해정도 및 사고요인별로 Event Tree를 작성하여 제시하였으며 이를 이용하여 중앙분리대 비교 1안(140cm) 및 비교 2안(127cm)에 대한 위험지수를 산정하였다.

에너지시설(도시가스배관)의 사고시 영향 평가 (Consequence Analysis of Energy Facility(City Gas Pipeline))

  • 박교식;이진한;조영도;박진희
    • 한국가스학회지
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    • 제7권1호
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    • pp.10-18
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    • 2003
  • 도시가스시설에서 사고가 발생할 때 그 영향을 평가하는 방법론에 대하여 현실을 고려한 모델을 개발하였다. 즉 사건수목분석(ETA)을 통하여 발생할 수 있는 사고의 형태를 도출하였고 가스의 누출 속도를 음속인 경우와 아음속인 경우에 대하여 계산하였다. 가스의 누출시 화재가 주로 피해를 유발하므로 화재가 발생하여 사망, 화상 및 건물에 피해를 줄 수 있는 경우 그 피해범위를 산정하는 방법을 제시하였다. 마지막으로 적절한 가정을 도입하여 사고로 인한 총 손실비용을 계산하는 방법을 제시하였다.

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Application plan for radiological exposure model using virtual reality-based radiological exercise system

  • Lee, Dewhey;Lee, Byung Il;Park, Younwon;Kim, Dohyung
    • Nuclear Engineering and Technology
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    • 제50권5호
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    • pp.745-750
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    • 2018
  • New exercise technology such as the virtual reality (VR)-based exercise system is required to meet soaring demand for target participants in exercises and to alleviate the difficulties in personnel mobilization through an alternative approach to the exercise system. In a previous study, event tree methodologies were introduced in setting up an exercise scenario of a VR-based radiological exercise system. In the scenario, the locations at which major events occur are rephrased as nodes, routes as paths, and public response actions as protective actions or contents of an exercise at individual locations. In the study, a model for estimating effective doses to the participants is proposed to evaluate the exercise system, using the effective dose rates at particular times and locations derived from a computer program. The effective dose received by a student when she/he follows a successful route is about a half of the dose received when she/he does not follow the exercise guide directions. In addition, elapsed time to finish an exercise when following a successful route is less than one-third of the time spent to finish an exercise when following the guide's directions.