원자력 발전소에 지진격리장치를 설치하여 내진성능을 향상시킬 수 있다. 그러나 지진격리장치의 적용으로 지반과 구조물 사이에서 큰 상대 변위가 발생하게 된다. 따라서 지진격리된 구조물과 일반 구조물을 연결하는 연결배관시스템의 경우 지진리스크가 증가할 수 있다. 따라서 이러한 배관시스템의 지진취약도를 분석할 필요가 있다. 본 연구에서는 지진취약도 분석 을 위해 지진격리된 APR1400 원자력발전소와 주증기관을 대상으로 지진취약도를 분석하였다. 주증기관은 지진격리된 nuclear island의 보조 건물과 터빈 건물을 연결하는 인터페이스 배관이다. 지진취약도 분석을 위한 파괴모드는 누출관통균열로 정의하였다. 누출은 실험결과와 수치해석을 통해 손상지수로 정량화하여 취약도 분석을 위한 파괴기준으로 사용하였다. 파괴기준의 변동에 의한 취약도 곡선의 변동성을 확인하기 위하여 손상지수의 최솟값, 최댓값, 평균값 및 중앙값을 파괴기준으로 하여 지진취약도 곡선을 작성하였다.

The purpose of this study is to investigate the effects of the significant duration of ground motions on responses of base-isolated nuclear power plants (NPPs). Two sets of ground motion records with short duration (SD) and long duration (LD) motions, scaled to match the target response spectrum, are used to perform time-history analyses. The reactor containment building in the Advanced Power Reactor 1400 (APR1400) NPP is numerically modeled using lumped-mass stick elements in SAP2000. Seismic responses of the base-isolated NPP are monitored in forms of lateral displacements, shear forces, floor response spectra of the containment building, and hysteretic energy of the lead rubber bearing (LRB). Fragility curves for different limit states, which are defined based on the shear deformation of the base isolator, are developed. The numerical results reveal that the average seismic responses of base-isolated NPP under SD and LD motion sets were shown to be mostly identical. For PGA larger than 0.4g, the mean deformation of LRB for LD motions was bigger than that for SD ones due to a higher hysteretic energy of LRB produced in LD shakings. Under LD motions, median parameters of fragility functions for three limit states were reduced by 12% to 15% compared to that due to SD motions. This clearly indicates that it is important to select ground motions with both SD and LD proportionally in the seismic evaluation of NPP structures.

In order to increase the seismic safety of nuclear power plant (NPP) structures, a technique to reduce the seismic load transmitted to the NPP structure by using a seismic isolation device such as a lead-rubber bearing has recently been actively researched. In seismic design of NPP structures, three directional (two horizontal and one vertical directions) artificial synthetic earthquakes (G0 group) corresponding to the standard design spectrum are generally used. In this study, seismic analysis was performed by using three directional artificial synthetic earthquakes (M0 group) corresponding to the maximum-minimum spectrum reflecting uncertainty of incident direction of earthquake load. The design basis earthquake (DBE) and the beyond design basis earthquakes (BDBEs are equal to 150%, 167%, and 200% DBE) of G0 and M0 earthquake groups were respectively generated for 30 sets and used for the seismic analysis. The purpose of this study is to compare seismic responses and seismic fragility curves of seismically isolated NPP structures subjected to DBE and BDBE. From the seismic fragility curves, the probability of failure of the seismic isolation system when the peak ground acceleration (PGA) is 0.5 g is about 5% for the M0 earthquake group and about 3% for the G0 earthquake group.

The seismically isolated nuclear power plants shall be designed for design basis earthquake (DBE) and considered to ensure safety against beyond design basis earthquake (BDBE). In order to limit the excessive displacement of the seismic isolation system of the seismically isolated structure, the moat is installed at a certain distance from the upper mat supporting the superstructure. This certain distance is called clearance to stop (CS) and is calculated from the 90th percentile displacement of seismic isolation system subjected to BDBE. For design purposes, the CS can be obtained simply by multiplying the median displacement of the seismic isolation system against DBE by scale factor with a value of 3. The DBE and BDBE used in this study were generated by using 30 sets of artificial earthquakes corresponding to the nuclear standard design spectrum. In addition, latin hyper cube sampling was applied to generate 30 sets of artificial earthquakes corresponding to maximum - minimum spectra. For the DBE, the median displacement and the 99th percentile displacement of the seismic isolation system were calculated. For the BDBE, the suitability of the scale factor was assessed after calculating the 90th percentile displacement of the seismic isolation system.

In order to improve the seismic performance of structures, friction pendulum system (FPS) is the most commonly used seismic isolation device in addition to lead rubber bearing (LRB) in high seismicity area. In a nuclear power plant (NPP) with a large self weight, it is necessary to install a large number of seismic isolation devices, and the position of the center of rigidity varies depending on the arrangement of the seismic isolation devices. Due to the increase in the eccentricity, which is the difference between the center of gravity of the nuclear structure and the center of stiffness of the seismic isolators, an excessive seismic response may occur which could not be considered at the design stage. Three different types of eccentricity models (CASE 1, CASE 2, and CASE 3) were used for seismic response evaluation of seismically isolated NPP due to the increase of eccentricity (0%, 5%, 10%, 15%). The analytical model of the seismic isolation system was compared using the equivalent linear model and the bilinear model. From the results of the seismic response of the seismically isolated NPP with increasing eccentricity, it can be observed that the effect of eccentricity on the seismic response for the equivalent linear model is larger than that for the bilinear model.

The Gyeong-Ju earthquake in the magnitude of 5.8 on the Richter scaleoccurred in September 12, 2016. Because there are many nuclear power plants (NPP) near the epicenter of the Gyeong-Ju earthquake, the seismic stability of nuclear power plants is becoming a social problem. In order to evaluate the safety of seismically isolated NPP, the seismic response of a NPP subjected to the Gyeong-Ju earthquake was compared with those of 30 sets of artificial earthquakes corresponding to the nuclear standard design spectrum (NSDS). A 2-node model and a simple beam-stick model were used for the seismic analysis of seismically isolated NPP structures. Using 2-node model, the effect of internal temperature rise, decrease of shear stiffness, increase of lateral displacement and decrease of vertical stiffness according to nonlinear behavior of lead-rubber bearing (LRB) were evaluated. The displacement response, the acceleration response, and the shear force response of the seismically isolated nuclear containment structure were evaluated using the simple beam-stick model. It can be observed that the seismic responses of the isolated nuclear structure subjected to Gyeong-Ju earthquake is significantly less than those to the artificial earthquakes corresponding to NSDS.

The Eradi Quake System (EQS) is a seismic isolation bearing system designed to minimize forces and displacements experienced by structures subjected to ground motion. The EQS dissipates seismic energy through friction of Poly Tetra Fluoro Ethylene (PTFE) disk pad. In general, a force-displacement relationship of EQS has post yield stiffness hardening during large inelastic displacement. In this study, seismic responses of seismically isolated nuclear power plant (NPP) subjected to design basis earthquake (DBE) and beyond design basis earthquakes (150% DBE and 167% DBE) are compared considering the post yield stiffness hardening effect of EQS. From the results, it can be observed that if the post-yield stiffness hardening effect of EQS is increased, the displacement response of EQS is reduced, and the acceleration and shear responses of containment structures of NPP is increased.

In order to improve seismic safety of nuclear power plant (NPP) structures in high seismicity area, seismic isolation system can be adapted. In this study, friction pendulum system (FPS) is used as the seismic isolation system. According to Coulomb‘s friction theory, friction coefficient is constant regardless of bearing pressure and sliding velocity. However, friction coefficient under actual situation can be changed according to bearing pressure, sliding velocity and temperature. Seismic responses of friction pendulum system with constant friction and various velocity-dependent friction are compared. The velocity-dependent friction coefficients of FPS are varied between lowand fast-velocity friction coefficients according to sliding velocity. From the results of seismic analysis of FPS with various cases of friction coefficient, it can be observed that the yield force of FPS becomes larger as the fast-velocity friction coefficient becomes larger. Also, the displacement response of FPS becomes smaller as the fast-velocity coefficient becomes larger.

In order to increase seismic performance of nuclear power plant (NPP) in strong seismic zone, lead-rubber bearing (LRB) can be applied to seismic isolation system of NPP structures. Simple equivalent linear model as structural analysis model of LRB is more widely used in initial design process of LRB than a bilinear model. Seismic responses for seismically isolated NPP containment structures subjected to earthquakes categorized into 5 different soil-site classes are calculated by both of the equivalent linear- and bilinear- LRB models and compared each others. It can be observed that the maximum displacements of LRB and shear forces of containment in the case of the equivalent linear LRB model are larger than those in the case of bilinear LRB model. From the seismic fragility curves of NPP containment structures isolated by LRB, it can be observed that seismic fragility in the case of equivalent linear LRB model are about 5~30 % larger than those in the case of bilinear LRB model.

It is very important to assure the seismic performance of equipment as well as building structures in seismic design of nuclear power plant(NPP). Seismically isolated structures may be reviewed mainly on the horizontal seismic responses. Considering the equipment installed in the NPP, the vertical earthquake responses of the structure also should be reviewed. This study has investigated the vertical seismic demand of seismically isolated structure by lead rubber bearings(LRBs). For the numerical evaluation of seismic demand of the base isolated NPP, the Korean standard nuclear power plant (APR1400) is modeled as 4 different models, which are supported by LRBs to have 4 different horizontal target periods. Two real earthquake records and artificially generated input motions have been used as inputs for earthquake analyses. For the study, the vertical floor response spectra(FRS) were generated at the major points of the structure. As a results, the vertical seismic responses of horizontally isolated structure have largely increased due to flexibility of elastomeric isolator. The vertical stiffness of the bearings are more carefully considered in the seismic design of the base-isolated NPPs which have the various equipment inside.

Base isolation is considered as a seismic protective system in the design of next generation Nuclear Power Plants (NPPs). If seismic isolation devices are installed in nuclear power plants then the safety under a seismic load of the power plant may be improved. However, with respect to some equipment, seismic risk may increase because displacement may become greater than before the installation of a seismic isolation device. Therefore, it is estimated to be necessary to select equipment in which the seismic risk increases due to an increase in the displacement by the installation of a seismic isolation device, and to perform research on the seismic performance of each piece of equipment. In this study, modified NRC-BNL benchmark models were used for seismic analysis. The numerical models include representations of isolation devices. In order to validate the numerical piping system model and to define the failure mode, a quasi-static loading test was conducted on the piping components before the analysis procedures. The fragility analysis was performed by using the results of the inelastic seismic response analysis. Inelastic seismic response analysis was carried out by using the shell finite element model of a piping system considering internal pressure. The implicit method was used for the direct integration time history analysis. In addition, the collapse load point was used for the failure mode for the fragility analysis.

In order to perform a soil-isolation-structure interaction analysis of seismically isolated nuclear power plant (NPP) structures, the nonlinear behavior of a seismic isolation system may be converted to an equivalent linear model used in frequency domain analysis. Seismic responses for seismically isolated NPP containment structures subjected to a simple artificial acceleration history and different site class earthquakes are evaluated for the equivalent-linear and nonlinear models that have been applied to lead-rubber bearing (LRB) modeling. It can be observed that the maximum displacements of the equivalent linear model are larger than that of the nonlinear model. From the floor response spectrum analysis for the top of NPP containment structures, it can be observed that the spectral acceleration of an equivalent linear model at about 0.5 Hz frequency is about 2~3 times larger than that of a nonlinear model.

면진장치는 지진력을 감소시키기 위하여 사용되어왔다. 원자력발전소에 면진장치가 적용된다면, 운영기간동안 구조물과 기기들은 동일한 내구성 및 성능이 확보되어야 한다. 본 연구에서는 면진된 원전의 지진에 대한 안전성을 확보하기 위하여 면진구조물의 장기거동을 해석적으로 분석하였다. 경년열화에 의한 면진장치 특성을 분석하였고, 다른 온도환경에서 면진장치의 경년열화에 의한 구조물의 지진응답을 분석하였다. 해석결과에 의하면 면진장치의 경년열화에 의하여 면진구조물의 고유진동수는 증가하였다. 그러나 면진 구조물의 최대가속도와 최대변위는 온도에 따라 크게 변하지 않았다. 면진장치의 열화에 의하여 구조물의 손상은 발생하지 않았지만 목표진동수 영역에서 스펙트럼가속도는 온도에 따라 증가하였다. 따라서 면진구조물에서 면진장치는 온도에 따른 지진응답의 증가를 고려하여 설치 및 제작해야 할 것으로 판단된다.

A methodology to evaluate the seismic performance of interface piping systems that cross the isolation interface in the seismically isolated nuclear power plant (NPP) was developed. The developed methodology was applied to the safety-related interface piping system to demonstrate the seismic performance of the target piping system. Not only the seismic performance for the design level earthquakes but also the performance for the beyond design level earthquakes were evaluated. Two artificial seismic ground input motions which were matched to the design response spectra and two historical earthquake ground motions were used for the seismic analysis of piping system. The preliminary performance evaluation results show that the excessive relative displacements can occur in the seismically isolated piping system. If the input ground motion contained relatively high energy in the low frequency region, we could find that the stress response of the piping system exceed the allowable stress level even though the intensity of the input ground motion is equal to the design level earthquake. The structural responses and seismic performances of piping system were varied sensitively with respect to the intensities and frequency contents of input ground motions. Therefore, for the application of isolation system to NPPs and the verification of the safety of piping system, the seismic performance of the piping system subjected to the earthquake at the target NPP site should be evaluated firstly.

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.

면진장치는 상부구조물의 지진력을 감소시키는데 크게 기여하지만, 고감쇠고무 적층받침에 사용되는 고무재료는 시간이 경과함에 따라 열화되어 상부구조물의 동특성과 기기들의 지진응답에 영향을 줄 수 있다. 따라서 면진장치의 경년열화를 고려한 구조물의 지진응답을 분석하는 연구가 필요하다. 본 연구에서는 기존 문헌을 통하여 분석된 고무의 경년열화 특성을 사용하여 면진장치를 모델링하였다. 면진된 원전의 지진응답을 평가하기 위하여 격납건물과 보조건물을 대상 구조물로 선정하고, 진동수 성분이 다양한 입력지진동을 사용하여 구조물의 고유진동수, 최대지진응답, 층응답스펙트럼을 시간의 경과에 따라 분석하였다. 해석결과에 의하면 면진장치의 경년열화에 의하여 지진응답이 소폭 증가하였으며, 면진장치가 설치된 후 20년까지 지진응답의 증가율이 크게 나타나므로 이 기간에 상세한 검사가 시행되어야 할 것이다.

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.

지금까지의 지진 관련 연구는 주로 교량 받침 자체의 성능개선이 주요 관심 과제였으나, 본 논문에서는 받침 종류에 따라 교량에 미치는 전반적인 지진거동 특성을 분석하고 교량 공사비에 미치는 영향을 검토하였다. 이를 위해 실무에서 많이 적용되는 PSC I형 교량에 대해 교량받침의 종류를 변화시키며 교각 높이를 매개변수로 하여 상시 및 지진해석을 수행하였다. 특히 지진해석을 통해 산출한 단면력을 고려하여 PSC I형 교량받침의 변위, 지진하중에 의한 교각 기둥의 직경, 상부여유 간격 등의 변화를 분석하였다. 고교각인 경우 탄성받침보다는 지진격리장치를 적용하는 것이 지진에 의한 상부구조의 이동량을 줄여 신축이음장치의 규격을 줄일 수 있으므로 차량의 주행성 및 교량의 유지관리 측면에서 바람직 할 것으로 판단되었고, 교량 하부 구조 단면이 축소되어 미관개선 및 경제성 개선의 효과가 있는 것으로 분석되었다. 결국, PSC I형 교량받침 설계시 일률적으로 탄성받침을 적용하는 것보다 정밀한 내진해석을 통해 지진격리장치를 적용하는 것이 구조적정성 측면 및 공사비 측면에서 타당하다는 결론에 도달하였다.

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.