• Title/Summary/Keyword: 확률론적 안전평가

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Probabilistic Seismic Risk Analysis of Breakwater Structures (방파제 구조물의 확률론적 지진위험도 분석)

  • Kim Sang-Hoon;Yi Jin-Hak;Kim Doo Kie
    • Journal of Korean Society of Coastal and Ocean Engineers
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    • v.17 no.1
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    • pp.32-40
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    • 2005
  • Recent earthquakes over magnitude 5 in the eastern coast of Korea have aroused interests in the earthquake analyses and seismic design of breakwater structures. Most of earthquake analysis methods such as equivalent static analysis, response spectrum analysis, nonlinear analysis, and capacity analysis methods are deterministic and have been used for seismic design and performance evaluation of breakwater structures. However, deterministic methods are difficult to reflect one of the most important characteristics of earthquakes, i.e. the uncertainty of earthquakes. This paper presents results of probabilistic seismic risk assessment(PSRA) of an actual caisson type breakwater structure considering uncertainties of earthquake occurrences and soil properties. First the seismic vulnerability of a structure and the seismic hazard of the site are evaluated using earthquake sets and seismic hazard map, and then seismic risk of the structure is assessed.

Probabilistic Safety Assessment of Gas Plant Using Fault Tree-based Bayesian Network (고장수목 기반 베이지안 네트워크를 이용한 가스 플랜트 시스템의 확률론적 안전성 평가)

  • Se-Hyeok Lee;Changuk Mun;Sangki Park;Jeong-Rae Cho;Junho Song
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.36 no.4
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    • pp.273-282
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    • 2023
  • Probabilistic safety assessment (PSA) has been widely used to evaluate the seismic risk of nuclear power plants (NPPs). However, studies on seismic PSA for process plants, such as gas plants, oil refineries, and chemical plants, have been scarce. This is because the major disasters to which these process plants are vulnerable include explosions, fires, and release (or dispersion) of toxic chemicals. However, seismic PSA is essential for the plants located in regions with significant earthquake risks. Seismic PSA entails probabilistic seismic hazard analysis (PSHA), event tree analysis (ETA), fault tree analysis (FTA), and fragility analysis for the structures and essential equipment items. Among those analyses, ETA can depict the accident sequence for core damage, which is the worst disaster and top event concerning NPPs. However, there is no general top event with regard to process plants. Therefore, PSA cannot be directly applied to process plants. Moreover, there is a paucity of studies on developing fragility curves for various equipment. This paper introduces PSA for gas plants based on FTA, which is then transformed into Bayesian network, that is, a probabilistic graph model that can aid risk-informed decision-making. Finally, the proposed method is applied to a gas plant, and several decision-making cases are demonstrated.

Probabilistic Analysis for Stability Evaluation of Landslides Using Geo-spatial Information (지형공간 정보를 활용한 산사태 안정평가의 확률론적 해석)

  • Park, Byung-Soo
    • Journal of Korean Society for Geospatial Information Science
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    • v.14 no.3 s.37
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    • pp.55-62
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    • 2006
  • The purpose of the current research is to evaluate the possibility of landslides by using geo-spatial information system. Geological information has been summarized and stability analysis for infinite slopes has been conducted based on the force equilibrium. In addition, the analysis of landslides was performed based on probabilistic approach by using probabilistic variables which can include uncertainty of input parameters. For the purpose of testifing the applicability of the analysis method actual geological data from a construction site was obtained, thereby performing both a preliminary analysis for a large area and detailed analysis for a better result. As a result of the current analysis several issues such as the possibility of development of landslides, detailed analysis of where landslides are most likely to be developed were analysed by using two concepts of safety and index of failure probability.

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A Deterministic Safety Assessment of a Pyro-processed Waste Repository (A-KRS 처분 시스템 결정론적 안전성 평가)

  • Lee, Youn-Myoung;Jeong, Jongtae;Choi, Jongwon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.10 no.3
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    • pp.171-188
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    • 2012
  • A GoldSim template program for a safety assessment of a hybrid-typed repository system, called "A-KRS," in which two kinds of pyro-processed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyro-processing of PWR nuclear spent fuels are disposed of, has been developed. This program is ready both for a deterministic and probabilistic total system performance assessment which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios. The A-KRS has been deterministically assessed with 5 various normal and abnormal scenarios associated with nuclide release and transport in and around the repository. Dose exposure rates to the farming exposure group have been evaluated in accordance with all the scenarios and then compared among other.

Seismic Safety Assessment of the Turbine-Generator Foundation using Probabilistic Structural Reliability Analysis (확률론적 구조신뢰성해석을 이용한 터빈발전기 기초의 지진 안전성 평가)

  • Joe, Yang-Hee;Kim, Jae-Suk;Han, Sung-Ho
    • Journal of the Earthquake Engineering Society of Korea
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    • v.12 no.2
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    • pp.33-44
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    • 2008
  • Most of the civil structure - bridges, offshore structures, plant, etc. - have been designed by the classical approaches which deal with all the design parameters as deterministic variables. However, some more advanced techniques are required to evaluate the inherent randomness and uncertainty of each design variable. In this research, a seismic safety assessment algorithm based on the structural reliability analysis has been formulated and computerized for more reasonable seismic design of turbine-generator foundations. The formulation takes the design parameters of the system and loading properties as random variables. Using the proposed method, various kinds of parametric studies have been performed and probabilistic characteristics of the resulted structural responses have been evaluated. Afterwards, the probabilistic safety of the system has been quantitatively evaluated and finally presented as the reliability indexes and failure probabilities. The proposed procedure is expected to be used as a fundamental tool to improve the existing design techniques of turbine-generator foundations.

Influence of Lateral Ballast Resistance on the Buckling Fragility Curve of the Continuous Welded Rail Tracks (장대레일 궤도의 좌굴 취약도 곡선에 대한 도상횡저항력의 영향)

  • Bae, Hyun Ung;Choi, Jin Yu;Lee, Chin Ok;Lim, Nam Hyoung
    • 한국방재학회:학술대회논문집
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    • 2011.02a
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    • pp.185-185
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    • 2011
  • 기존 장대레일 궤도의 안정성 평가는 궤도 매개변수에 대하여 고정된 안전측의 값을 사용하는 결정론적인 해석에 의존해서 평가되어져 왔다. 그러나 실제현장의 궤도조건은 많은 영향인자들에 의해 그 특성이 불확실하게 변하고 있다. 따라서 온도하중에 의한 궤도 좌굴에 영향을 미치는 궤도 구성인자들의 불확실성 및 임의성을 보다 합리적으로 고려하기 위해서 확률론적 기법을 적용하는 것이 필수적이다. 본 연구에서는 기존 본 연구진에 의해 개발된 장대레일 궤도의 좌굴확률 평가시스템을 이용하여 좌굴 취약도 곡선을 나타내었으며, 궤도 좌굴에 영향을 미치는 주요변수 중 하나인 도상횡저항력에 대한 영향을 분석하였다. 좌굴확률 평가시스템에서는 장대레일 궤도의 좌굴확률을 산정하기 위하여 구조물의 안정과 파괴를 판단할 수 있는 기준을 한계상태방정식으로 표현하고, 이 한계상태방정식으로부터 확률론적 기법 중 하나인 AFOSM(Advanced First Order Second Moment) 방법을 이용하여 파괴확률의 간접적인 지표인 신뢰도지수(${\beta}$)를 통해 좌굴확률을 계산한다. 한계상태방정식에서 구조물의 강도(보유성능)에 해당하는 부분은 궤도의 허용좌굴온도이고, 하중(요구성능)에 해당하는 부분은 레일온도하중으로써 현재 레일온도와 중립온도의 차로 반영된다. 허용좌굴온도 산정에 고려되는 주요변수는 곡선반경(Radius), 도상횡저항력(Lateral Ballast Resista nce), 연직도상강성(Vertical Ballast Stiffness), 궤도 틀림량(Misalignment), 틀림길이(Half Wave Length), 열차운행속도(Velocity)이다. 각 확률변수들이 갖는 확률분포는 모두 정규분포로 가정하였다. 궤도의 기하학적 특성은 곡선반경 5,000m에 대해 고려하였으며, 열차는 KTX의 제원을 사용하여 정지된 상태에서 고려하였다. 틀림량과 틀림길이는 이에 대한 통계적 특성자료가 부족하여 확률변수로 고려하지 않고 결정론적 값으로 취급하였다. 레일온도의 통계적 특성치는 본 연구진에 의해 구축된 기후요소 및 레일온도 DB를 근거로 결정하였으며, 중립온도는 선로관리지침에 따라 $25{\pm}3^{\circ}C$를 기준으로 결정하였다. 또한 도상횡저항력은 실측 데이터를 참고로 하여 평균값에서 10%의 변동량을 갖는 것으로 보고 통계적 특성치를 결정하였다. 도상횡저항력이 좌굴확률에 미치는 영향을 매우 큰 것을 알 수 있었으며, 레일온도 $60^{\circ}C$일 때 도상횡저항력이 증가하면서 감소되는 좌굴확률이 도상저항력이 커질수록 그 감소량이 작아지는 것을 알 수 있었다.

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Groundwater Flow Analysis for a Block Cavern Type Radwaste Repository (방사성폐기물 동굴처분 안전성 평가를 위한 지하수 유동 평가)

  • 황용수;서은진;강철형
    • Tunnel and Underground Space
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    • v.14 no.3
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    • pp.203-214
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    • 2004
  • For total system performance of a potential radwaste repository, a hypothetical site is assumed with feasible boundary conditions. Assuming a coastal repository, the sensitivity of the depth and the location of a repository along with the distance to a joint on groundwater transport pathways is studied. Results from Connectflow analysis could be used as input of the MASCOT-t the probabilistic safety assessment code.

Study of Probabilistic Tsunami Hazard Analysis(PTHA) for Tsunami Hazard Assessment at Nuclear Power Plant (원자력발전소의 지진해일 위험도 평가를 위한 확률론적 지진해일 재해도 분석(PTHA))

  • Kim, Byung-Ho;Jeong, Hyun-Kee;Cho, Yong-Sik
    • Proceedings of the Korea Water Resources Association Conference
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    • 2021.06a
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    • pp.215-215
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    • 2021
  • 인도네시아 수마트라 지진해일(2004년)과 동일본 대지진(2011년)으로 인해 해당지역에서 막대한 인적·물적 피해가 발생하였으며, 지진해일에 대한 사람들의 경각심은 더욱 커지게 된 계기가 되었다. 반면 우리나라는 지진이 빈번하게 발생하는 국가에 비해 상대적으로 지진해일에 대해 안전하다는 국민들의 인식이 강한 것이 사실이다. 하지만 최근 우리나라에서 크고 작은 지진이 발생(2016년 경주 지진, 2017년 포항 지진 등)함에 따라 국민들은 지진 및 지진해일 안전에 대한 경각심이 높아지고 있다. 또한 한반도 주변에서 지진은 끊임없이 발생하고 있으며, 과거 우리나라는 지진해일로 인한 인명 및 재산피해가 기록된 사례도 존재한다(Cho, 2018). 본 연구에서는 원자력 발전소에서 지진해일에 대한 위험성에 대비하기 위해 지진해일 수치모형 실험을 통해 계산된 지진해일고 결과값에 대해 적절한 확률분포 모형을 개발한 후 각 지진해일 시나리오의 연초과 확률을 분석함으로써, 확률론적 지진해일 재해도 분석(PTHA : Probabilistic Tsunami Hazard Analysis)을 실시하는 것이다. 최종적으로는 연구대상지역의 지진해일 안전성 평가에 기여할 수 있는 검증된 자료를 제공한다. PTHA 분석은 미국(Park and Cox, 2016), 인도네시아(Horspool et al., 2014), 남유럽(Lorito et al., 2014), 일본(Japan Society of Civil Engineers, 2016) 등에서 연구가 활발하게 이루어졌으며 현재도 활발한 연구가 진행되고 있다. 본 논문에서는 먼저, 역사 지진해일 및 우리나라 근해에서 발생가능한 지진원(단층매개변수) 조사, 그리고 지진해일 수치모형실험 case 선정을 위한 파향선추적모형(wave ray-tracing) 수행, 마지막으로 지진해일고의 불확실성을 고려하기 위한 로직트리(Logic-Tree)기법 적용 시 사용하게 될 지진해일 단층매개변수 선정을 위한 지진해일 수치모형 실험 등을 수행한다.

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A Shaking Table Test for an Re-evaluation of Seismic Fragility of Electrical Cabinet in NPP (원전 전기캐비넷의 지진취약도 재평가를 위한 진동대 실험)

  • Kim, Min-Kyu;Choi, In-Kil
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.24 no.3
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    • pp.295-305
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    • 2011
  • In this study, a seismic behavior of electrical cabinet system in Nuclear Power Plants(NPPs) was evaluated by the shaking table test. A 480V Motor Control Centers(MCCs) was selected for the shaking table test, and a real MCC cabinet for the Korea Nuclear Power Plant site was rented by manufactured company. For the shaking table tests, three kinds of seismic input motions were used, which were a US NRC Reg. guide 1.60 design spectrum, a UHS spectrum and PAB 165' floor response spectrum(FRS). Especially, the UHS input motion was selected for an evaluation of structural seismic amplification effects, three directional accelerations were measured at three points outside on the cabinet system and also that of the incabinet response amplification, accelerations were measure at two points which were mounted in electrical equipment such as relay. Seismic amplification effect is determined at the outside and inside of a cabinet as input seismic motion, and compared to the results which are calculated by analytical method based on NUREG/CR-5203.