• Title/Summary/Keyword: 확률론적 안전평가

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Reliability Estimation of Steam Turbine Blade Using First Order Reliability Method (FORM을 이용한 증기 터빈블레이드의 신뢰성 평가)

  • 황진호;김철수;김정규
    • Proceedings of the Korean Reliability Society Conference
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    • 2002.06a
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    • pp.199-204
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    • 2002
  • 본 연구에서는 저압 증기 터빈블레이드의 안전성 확보를 위하여 작용응력 및 강도의 변동성을 고려한 확률론적 해석을 수행하였다. 정상상태에서 작용응력은 이론 및 유한요소해석에 의해서 얻을 수 있으며, 최대 von-Mises 응력은 215.4MPa이다. 회전굽힘 하중하에서의 피로한도는 응력비 R= -1에서 계단식 시험법을 이용하여 구하였으며, 이의 확률론적 특성에 가장 적합한 분포는 3 모수 와이블 분포이다. 그리고 신뢰성에 미치는 다양한 인자들의 영향은 영향계수(sensitivity factor)를 이용하여 정량적으로 평가하였다.

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Importance Analysis of High Pressure Safety Injection System to CDF of Yonggwang units 3\ulcorner\ulcorner4 (영광 1,2호기 고압안전주입계통 중요도 분석)

  • 조성환;김명기;서미로
    • Proceedings of the Korea Society for Energy Engineering kosee Conference
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    • 1998.05a
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    • pp.159-165
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    • 1998
  • The RCM strategies are considered as an effective maintenance tool in nuclear power plants to allocate limited resource efficiently. In this paper, the importances of HPSI system on the CDF were analyzed with PSA model of Yonggwang units 1,2. The HPSI system was chosen because it is of one of the pilot system for the study of Yonggwang units 1,2 RCM. With the remodeling of the HPSI system, the total CDF of 16 initiating events was quantified and the importance of 74 basic events of HPSI was analyzed.

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울진 3,4호기 ESW 펌프 On-Line Maintenance분석

  • 김길유;한상훈;장승철;김태운
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.606-610
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    • 1997
  • 울진 원전 3,4 호기 확률론적 안전성 평가 (PSA) 모델을 risk monitor 모델로 변환하여 한국원자력연구소에서 개발한 risk monitor인 Risk Monster[1]에 설치하였으며 이를 이용하여 필수냉각수 계통(ESW;Essential Service Water) 펌프의 가동중 정비(on-line maintenance)의 가능성 여부를 연구하였다. ESW 펌프를 가동중 정비하더라도 안전성 측면에서 별 문제가 없으며 경제성 여부는 보다 정확한 검토가 요구되나 상당히 있는 것으로 판단된다. 한편 ESW펌프 한대의 고장이 원전 가동중에 미치는 위험도를 분석하였으며 그 결과 ESW펌프 한대의 고장에도 불구하고 원전 계속 가동에는 큰 문제가 없었다.

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Probabilistic Analysis for Rock Slope Stability Due to Weathering Process (풍화작용에 따른 암반사면 안정성의 확률론적 해석)

  • Park, Hyuck-Jin;Woo, Ik;Um, Jeong-Gi
    • Economic and Environmental Geology
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    • v.42 no.4
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    • pp.357-366
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    • 2009
  • Since weathering weakens the rock fabric and exaggerates any structural weakness, it affects mechanical properties as well as physical and chemical properties of rock. Weathering leads to a decrease in density, strength, friction angle and cohesion, and subsequently it affects negatively on the stability of rock slope. The purpose of the study is to investigate the changes of the rock slope stability caused by discontinuities which have different weathering grades. For that, the discontinuity samples which are divided into two different weathering grades are obtained from the field and tested their mechanical properties such as JCS, JRC and residual friction angle. In order to evaluate the effects on the stability of slope due to weathering, the deterministic analysis is carried out. That is, the factors of safety for planar failure are calculated for rock masses which have two different weathering grades, such as fresh and weathered rock mass. However, since the JRC and friction angle values are widely scattered and the deterministic analysis cannot consider the variation, the factors of safety cannot represent properly the stability of the rock slope. Therefore, the probabilistic analysis has been used to consider the scattered values. In the deterministic analysis, the factors of safety for the fresh discontinuity and weathered discontinuity are 1.25 and 1.0, respectively. The results indicate the fresh discontinuities are stable for planar failure and the weathered discontinuities are marginally stable. However, the probabilities of failure for the fresh discontinuity and weathered discontinuity are 25.6% and 45.9%, respectively. This shows that both discontinuities are analyzed as unstable in the probabilistic analysis.

Seismic Fragility Analysis of PSC Containment Building by Nonlinear Analysis (비선형 지진해석에 의한 PSC 격납건물의 지진취약도 분석)

  • Choi, In-Kil;Ahn, Seong-Moon;Choun, Young-Sun
    • Journal of the Earthquake Engineering Society of Korea
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    • v.10 no.1 s.47
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    • pp.63-74
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    • 2006
  • The seismic fragility analysis method has been used as a quantitative seismic safety evaluation method for the NPP(Nuclear Power Plant) structures and equipments. The seismic fragility analysis gives a realistic seismic capacity excluding the convertism included in the design stage. The conservatism is considered as the probabilistic parameters related to the response and capacity in the seismic fragility analysis. In this study, the displacement based seismic fragility analysis method was proposed based on the nonlinear dynamic analysis results. In this study, the seismic safety of the prestressed concrete containment building of KSNP(Korean Standard Nuclear Power Plant) was evaluated for the scenario earthquakes, neat-fault, far-fault, design earthquake and probability based scenario earthquake, which can be occurred in the NPP sites.

철도 안전관리 개선을 위한 확률론적 위험도 평가 방안의 고찰

  • 곽상록;왕종배;홍선호
    • Journal of the Korean Society for Railway
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    • v.6 no.4
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    • pp.11-18
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    • 2003
  • 우리는 복잡한 현상을 하나의 수치로 표현하는 각종 지표(index)를 생활에서 많이 접하고 있다. 종합주가 지수, 불쾌지수, 소비자 물가지수, 년간 교통사고 건수, 인구 10만명당 교통사고 사망자수 등도 일종의 지표라 할 수 있다. 철도에서도 위험을 평가하는 지표로는 "년간 사고건수", "열차운행 100만-km당 사고건수"와 같이 발생빈도에 초점을 둔 경우와 "년간 사망자수", 혹은 "피해액", "운행지장"과 같이 사고피해에 초점을 둔 경우가 있다. (중략)

The Development of a Human Reliability Analysis System for Safety Assessment of a Nuclear Power Plants (원자력 발전소 안전성 평가를 위한 인간 신뢰도 분석 방법론 개발 및 지원 시스템 구축)

  • Kim, Seung-Hwn;Jung, Won-Dea
    • Journal of the Korea Society of Computer and Information
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    • v.11 no.6 s.44
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    • pp.261-267
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    • 2006
  • In order to perform a probabilistic safety assessment (PSA), it requires a large number of data for various fields. And the quality of a PSA results have become more important thing of the risk assessment. As part of enhancing the PSA qualify, Korea Atomic Energy Research Institute is developing a full power Human Reliability Analysis (HRA) calculator to manage human failure events (HFEs) and to calculate the diagnosis human error probabilities and execution human error probabilities. This paper introduces the development process and an overview of a standard HRA method for nuclear power plants. The study was carried out in three stages; 1) development of the procedures and rules for a standard HRA method. 2) design of a system structure, 3) development of the HRA calculator.

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Optimum Service Life Management Based on Probabilistic Life-Cycle Cost-Benefit Analysis (확률론적 생애주기비용-이익분석 기반 수명관리 최적화 기법)

  • Kim, Sunyong
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.17 no.4
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    • pp.19-25
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    • 2016
  • Engineering structures including civil infrastructures require a life-cycle cost and benefit during their service lives. The service life of a structure can be extended through appropriate inspection and maintenance actions. In general, this service life extension requires more life-cycle cost and cumulative benefit. For this reason, structure managers need to make a rational decision regarding the service life management considering both the cost and benefit simultaneously. In this paper, the probabilistic decision tool to determine the optimal service life based on cost-benefit analysis is presented. This decision tool requires an estimation of the time-dependent effective cost-benefit under uncertainty to formulate the optimization problem. The effective cost-benefit is expressed by the difference between the cumulative benefit and life-cycle cost of a deteriorating structure over time. The objective of the optimization problem is maximizing the effective cost-benefit, and the associated solutions are the optimal service life and maintenance interventions. The decision tool presented in this paper can be applied to any deteriorating engineering structure.

시스템 다이나믹스를 활용한 원전 조직 인자의 정량화 방법 연구

  • 유재국;윤태식
    • Nuclear industry
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    • v.23 no.6 s.244
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    • pp.48-56
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    • 2003
  • 본 연구의 목표는 원전의 안전성 확보에 기여할 수 있는 조직 및 인적 요인의 평가에 대한 시스템 다이나믹스(System Dynamics) 모델을 만드는데 있다. 기존의 연구는 크게 인간 공학 혹은 확률론적 안전성 평가와 같은 공학적 방법과 조직 사회학적 접근으로 구분할 수 있다. 양 방법은 조직 및 인적 요인이 무엇인지를 밝혀주고 인적 실수를 줄이기 위한 지침을 제공해 준다. 그러나 인자들간의 상호 독립성의 가정은 원전에서 일어나고 있는 요인들간의 상호 작용을 설명하는데 어려움을 지닌다. 이러한 제약 사항을 극복하기 위해서 조직 및 인적 요인 사이의 인과 관계를 보여줄 수 있는 시스템 다이나믹스 모델을 개발하였다. 개발된 모델을 통하여 리더십, 직원 수의 조정, 각 부서별 업무량의 조정 등을 조작하면서 모델의 사용자들은 조직 측면에서 원전의 안전성이 어떻게 변화하는가를 확인할 수 있다. 시뮬레이션을 통해서 사용자들은 관리적인 시사점을 얻을 수 있을 것이다.

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Evaluation of Human Reliability Analysis Results in Probabilistic Safety Assessment for Korea Standard Nuclear Power Plants (표준 원자력발전소 확률론적 안전성 평가의 인간 신뢰도 분석 평가)

  • 강대일;정원대;양준언
    • Journal of the Korean Society of Safety
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    • v.18 no.2
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    • pp.98-103
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    • 2003
  • Based on ASME probabilistic risk assessment (PRA) and NEI PRA peer review guidance, we evaluate a human reliability analysis (HRA) in probabilistic safety assessment (PSA) for Korea standard nuclear power plants, Ulchin Unit 3&4, to improve it performed at under design. The HRA for Ulchin Unit 3&4 is assessed as higher than Grade I based on ASME PRA standard and as higher than Grade 2 based on NEI PRA peer review guidance. The major items to be improved identified through the evaluation process are the documentation, the systematic human reliability analysis, the participitation of operators in the works and review of HRA. We suggest the guidance on the identification and qualitative screening analysis for pre-accident human errors and solve some items to be improved using the suggested guidance.