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.

이 연구는 기초의 묻힘이 면진 원전구조물의 응답에 미치는 효과를 지표기초와 비교하여 평가하였다. 면진장치의 비선형 성을 고려한 비선형 SSI 해석은 진동수영역해석과 시간영역해석의 복합법인 경계반력법(BRM)을 이용하여 수행하였다. BRM 해석모델은 BRM을 이용한 등가선형 SSI 해석결과를 재래의 주파수영역 SSI 해석결과와 비교함으로 검증하였다. 마 지막으로 비선형 SSI해석에 의한 묻힌기초 모델의 면진장치의 변위 및 구조물 응답을 지표기초의 해석결과와 비교하였다. 비교결과, 면진장치의 변위응답은 묻힌기초효과를 고려할 경우 감소할 수 있음을 알 수 있었다.

In this paper, firstly, acceleration-time histories were generated by varying strong motion duration in the frequency domain for application to a seismically isolated nuclear power structure, so as to examine the effects of strong motion duration on the behavior of the structure. Secondly, real recorded earthquakes were modified to match the target response spectrum based on the revised SRP 3.7.1(2007) and the modified time histories were applied to the analysis of a seismically isolated nuclear power structure. The obtained values of acceleration and displacement responses of the structure were, finally, compared with the values obtained in case of applying acceleration-time histories generated in the frequency domain to the structure.

Several researches have been studied to enhance the seismic performance of nuclear power plants (NPPs) by application of seismic isolation. If a seismic base isolation system is applied to NPPs, seismic performance of nuclear power plants should be reevaluated considering the soil-structure interaction effect. The seismic fragility analysis method has been used as a quantitative seismic safety evaluation method for the NPP structures and equipment. In this study, the seismic performance of an isolated NPP is evaluated by seismic fragility curves considering the soil-structure interaction effect. The designed seismic isolation is introduced to a containment building of Shin-Kori NPP which is KSNP (Korean Standard Nuclear Power Plant), to improve its seismic performance. The seismic analysis is performed considering the soil-structure interaction effect by using the linearized model of seismic isolation with SASSI (System for Analysis of Soil-Structure Interaction) program. Finally, the seismic fragility is evaluated based on soil-isolation-structure interaction analysis results.

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.

This paper addresses simplified method for nonlinear soil–structure interactions (SSI) analysis of base-isolated nuclear power plant (NPP) structure under incident seismic waves. The accuracy and applicability of the method are evaluated by comparing with nonlinear time history responses obtained by the boundary reaction method (BRM).

This paper addresses simplified method for nonlinear soil–structure interactions (SSI) analysis of base-isolated nuclear power plant (NPP) structure under incident seismic waves. The accuracy and applicability of the method are evaluated by comparing with nonlinear time history responses obtained by the boundary reaction method (BRM).

The ex-vessel steam explosion may occur when, during a severe reactor accident, the molten core pours into the water in the reactor cavity. These dynamic loads on the cavity wall could potentially lead to the significant failure of the cavity wall. But the phenomenon like this steam explosion includes big uncertainty in estimating the impulsive pressure loading of RCB. In this study, risk based integrity assessment method of the NPP structure subjected to steam explosion load was suggested to capture these uncertainties involved during the structural integrity assessment of the Nuclear power plant.

In this study, the investigation of the local damage evaluation method for the SC structure subjected to impact load was carried out. The conventional RC formula and SC formula to calculate wall thickness to prevent perforation were studied and compared. Finally, these results were compared with finite element analysis results using LS-Dyna, and the future direction to develop the reasonable local damage evaluation method of the NPP SC structure was suggested.

In this study, sensitivity analysis to investigate the effect on analytical results of the aircraft impact analysis parameter for the nuclear power plant was carried out. Verification of the analytical model and method using the test results was performed. The eroding parameter of the Winfrith concrete material model in LS-Dyna and modelling method of the SC wall structure were studied. Finally, these results are to be used for the development of the structural safety evaluation procedure for the aircraft impact on the nuclear power plant.

According to NEI 07-13 R8, in aircraft impact analysis for new plant design, global structural damage of the target structure can be evaluated analytically using one of the following methods of evaluation: 1) Force time-history analysis method. 2) Missile-target interaction analysis method. It depends on the availability of data on the dynamic characteristics and the intended level of detail of analysis. The purpose of this study is to evaluate the effect on the analytical results of the aircraft impact analysis method. Several impact analyses using various method were performed for the simplified external SC wall of the APR+ nuclear power plant structure.