• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1331-1344
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• 2021

This study is to evaluate the seismic capacity of the fire-damaged cabinet facility in a nuclear power plant (NPP). A prototype of an electrical cabinet is modeled using OpenSees for the numerical simulation. To capture the nonlinear behavior of the cabinet, the constitutive law of the material model under the fire environment is considered. The experimental record from the impact hammer test is extracted trough the frequency-domain decomposition (FDD) method, which is used to verify the effectiveness of the numerical model through modal assurance criteria (MAC). Assuming different temperatures, the nonlinear time history analysis is conducted using a set of fifty earthquakes and the seismic outputs are investigated by the fragility analysis. To get a threshold of intensity measure, the Monte Carlo Simulation (MCS) is adopted for uncertainty reduction purposes. Finally, a capacity estimation model has been proposed through the investigation, which will be helpful for the engineer or NPP operator to evaluate the fire-damaged cabinet strength under seismic excitation. This capacity model is presented in terms of the High Confidence of Low Probability of Failure (HCLPF) point. The results are validated by the proper judgment and can be used to analyze the influences of fire on the electrical cabinet.

• 한국지진공학회논문집
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• 제23권6호
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• pp.301-309
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• 2019

A methodology to assess seismic fragility of a nuclear power plant (NPP) using a conditional mean spectrum is proposed as an alternative to using a uniform hazard response spectrum. Rather than the single-scenario conditional mean spectrum, which is the conventional conditional mean spectrum based on a single scenario, a multi-scenario conditional mean spectrum is proposed for the case in which no single scenario is dominant. The multi-scenario conditional mean spectrum is defined as the weighted average of different conditional mean spectra, each one of which corresponds to an individual scenario. The weighting factors for scenarios are obtained from a deaggregation of seismic hazards. As a validation example, a seismic fragility assessment of an NPP containment structure is performed using a uniform hazard response spectrum and different single-scenario conditional mean spectra and multi-scenario conditional mean spectra. In the example, the number of scenarios primarily influences the median capacity of the evaluated structure. Meanwhile, the control frequency, a key parameter of a conditional mean spectrum, plays an important role in reducing logarithmic standard deviation of the corresponding fragility curves and corresponding high confidence of low probability of failure (HCLPF) capacity.

• 한국전산구조공학회논문집
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• 제25권1호
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• pp.57-64
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• 2012

방사성폐기물의 처리과정에서 발생한 설계하중 이상의 지진은 방사성 물질을 외부로 노출시킬 수 있으므로 방사성폐기물 처분장은 설계시 지진에 대하여 충분한 여유도를 가지도록 설계되어야 한다. 본 연구에서는 방폐장의 지상구조물에 대한 지진성능을 평가하기 위하여 지진 취약도 분석을 수행하였다. 지진 취약도 평가에 의하면, 해석모델로 선정된 인수저장 시설과 방사성폐기물 건물은 장방형의 구조물로써 구조물의 축에 따라 지진 성능이 약 23%~43% 다르게 나타났다. 최소 손상수준을 기준으로 할 경우 인수저장시설과 방사성폐기물 건물의 HCLPF성능은 각각 0.52g와 0.93g로 나타났으며, 방사성폐기물 건물은 원전의 격납건물과 유사한 지진성능을 보였다.

• 한국지진공학회논문집
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• 제11권6호
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• pp.69-78
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• 2007

본 연구에서는 원자력발전소 비상디젤발전기의 내진안전성을 정량적으로 평가하기 위하여 지진취약도 분석방법을 제안하고 제안한 방법을 이용하여 비상디젤발전기의 지진취약도를 평가하여 정량적인 지진위험도를 제시하였다. 기존의 비상디젤발전기뿐만 아니라 면진장치를 설치하여 지진력 저감효과를 증대시킨 비상디젤발전기에 대한 지진취약도 분석을 함께 수행하여 비상디젤발전기와 같은 대형 회전기기의 경우 면진장치를 통한 지진취약도의 변화를 살펴보았다. 최종적으로 지진취약도 결과를 이용하여 HCLPF값의 변화를 비교하여 면진에 의하여 비상디젤발전기의 취약도를 크게 개선 할 수 있는 것을 알 수 있었으며, 면진된 경우 면진장치의 파괴가 전체 거동을 지배하므로 면진장치의 성능개선이 필요한 것을 알 수 있었다.

• 한국지진공학회논문집
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• 제5권5호
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• pp.47-56
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• 2001

원전 격납건물은 내진 안정성을 확보하기 위해 설계단계에서 여유나 보수성을 부여하게 된다. 원전 구조물의 내진성능 평가는 이러한 여유나 보수성을 배제한 실질적인 성능 및 응답을 기준으로 평가하게 된다. 본 연구에서는 내진성능 평가에 고려되는 구조물의 성능 및 응답관련 계수들 중 그 기여도가 비교적 큰 비탄성 에너지 흡수계수의 산정방법에 대한 비교를 수행하였다. 또한 각종 방법에 따라 산정된 비탄성 에너지 흡수계수에 따른 HCLPF(high confidence of low probability of failure)값의 변화를 분석하였다. 연구결과 원전 격납건물의 비탄성 에너지 흡수계수는 1.5~1.75로 나타났다. 구조물의 내진성능을 명확히 평가하기 위해서는 먼저 구조물의 비선형 거동 및 연성도를 정확히 평가하여야 함을 알 수 있다.

• Earthquakes and Structures
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• 제15권3호
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• pp.295-306
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• 2018

Reinforced concrete containment (RCC) building has long been considered as the last barrier for keeping the radiation from leaking into the environment. It is important to quantify the performance of these structures and facilities considering extreme conditions. However, the preceding research on evaluating nuclear power plant (NPP) structures, particularly considering mainshock-aftershock seismic sequences, is deficient. Therefore, this manuscript serves to investigate the seismic fragility of a typical RCC building subjected to mainshock-aftershock seismic sequences. The implementation of the fragility assessment has been performed based on the incremental dynamic analysis (IDA) method. A lumped mass RCC model considering the tri-linear skeleton curve and the maximum point-oriented hysteretic rule is employed for IDA analyses. The results indicate that the seismic capacity of the RCC building would be overestimated without taking into account the mainshock-aftershock effects. It is also found that the seismic capacity of the RCC building decreases with the increase of the relative intensity of aftershock ground motions to mainshock ground motions. In addition, the effects of artificial mainshock-aftershock ground motions generated from the repeated and randomized approaches and the polarity of the aftershock with respect to the mainshock on the evaluation of the RCC are also researched, respectively.

• 한국전산구조공학회논문집
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• 제27권2호
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• pp.103-111
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• 2014

본 연구에서는 비선형 유한요소 해석 기법을 적용한 격납건물의 내압취약도 평가를 수행하였다. 대상 구조물은 국내 대표적인 가압경수로형 원전 격납건물 중 하나로 하였다. 비선형 극한내압 해석을 위해 대규모 개구부를 고려한 격납건물의 3차원 유한요소 모델을 도출하였다. 재료 특성 및 구조적 성능에 내포된 불확실성을 고려하기 위하여 각 변수들의 변동성에 대한 극한내압 성능의 민감도 해석을 수행하였다. 민감도 해석 결과를 통해 확률론적 내압 취약도 평가를 위한 불확실성 변수 및 분포 특성을 도출하였다. 현재의 텐던 긴장력 상태를 고려하기 위하여 가동 중 검사 보고서에 기록된 텐던 긴장력 값을 중앙값으로 적용하였다. 누설(leak)과 파단(rupture)을 파괴모드로 정의하고, 각각에 대한 극한내압 취약도 평가를 위하여 한계상태를 정의하였다. 각 파괴모드에 대한 대상 격납건물의 내압취약도를 내압 성능 중앙값, 고신뢰도 저파괴확률 성능값, 신뢰도 수준에 따른 취약도 곡선을 통하여 제시하였다. 누설 및 파단 파괴모드에 대한 고신뢰도 저파괴확률값은 각각 0.7991 MPa, 0.8691 MPa로 평가되었다.

• 한국지진공학회:학술대회논문집
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• 한국지진공학회 2000년도 춘계 학술발표회 논문집 Proceedings of EESK Conference-Spring
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• pp.97-104
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• 2000

Evaluating a Review-Level Ground Motion is a key to efficiently perform Seismic Margin Assessment of nuclear power plants whose purpose is to determine a ground motion level for which a plant has high-confidence-of-a-low-probability of seismic-induced core damage and to identify any weaker-link components. In this study a method to obtain RLGMs is reviewed which is recommended by Electric Power Research Institute and implemented to be applied to Limerick site in eastern and central U. S as a case study. This method provides reasonable and site-specific RLGMs as minimum required plant HCLPF for SMA that meet a target mean seismic core-damage frequency based on seismic hazard results and generic values of uncertainty and randomness parameters of the core-damage fragility curves. In addition high-frequency RLGM is justifiably modified to reflect the increased seismic capacity of high-frequency components and spatial variation and incoherence of input ground motion on a basemat of large structures by establishing a method to obtain high0-frequency reduction factors according to EPRI guidelines.

• 한국지진공학회:학술대회논문집
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• 한국지진공학회 2005년도 학술발표회 논문집
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• pp.453-460
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• 2005

In this study, the seismic fragility analysis of a base isolated condensate storage tank installed in the nuclear power plant. The condensate storage tank is safety related structure in a nuclear power plant. The failure of this tank affect significantly to the core damage frequency of the nuclear power plants. The seismic analysis of the liquid storage tank was performed by the simple calculation method and the dynamic time storage analysis method. The convective and impulsive fluid mass is modeled as added masses proposed by several researchers. To evaluate the effectiveness of the isolation system, the comparison of HCLPF and core damage frequencies in non-isolated and isolated cases are carried out. It can be found from the results that the seismic isolation system increases the seismic capacity of a condensate storage tank and decreases the core damage frequency significantly.

• Nuclear Engineering and Technology
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• 제54권1호
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• pp.386-400
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• 2022

Seismic fragility analysis, a part of seismic probabilistic risk assessment (SPRA), is commonly used to establish the relationship between a representative property of earthquakes and the failure probability of a structure, component, or system. Current guidelines on the SPRA of nuclear power plants (NPPs) used worldwide mainly reflect the earthquake characteristics of the western United States. However, different earthquake characteristics may have a significant impact on the seismic fragility of a structure. Given the concern, this study aimed to investigate the effects of earthquake characteristics on the seismic fragility of concrete containments housing the OPR-1000 reactor. Earthquake time histories were created from 30 ground motions (including those of the 2016 Gyeongju earthquake) by spectral matching to the site-specific response spectrum of Hanbit nuclear power plants in South Korea. Fragility curves of the containment structure were determined under the linear response history analysis using a lumped-mass stick model and 30 ground motions, and were compared in terms of earthquake characteristics. The results showed that the median capacity and high confidence of low probability of failure (HCLPF) tended to highly depend on the sustained maximum acceleration (SMA), and increase when using the time histories which have lower SMA compared with the others.