본 논문에서는 OpenSees 프로그램을 이용한 콘크리트 교량의 지진취약성 분석 방법에 대한 고찰을 제시한다. 교각 및 휨 부재 분산 비선형(distributed plasticity) 요소를 적용한 해석모델을 활용하여 지진에 대한 응답을 구하고 이를 통계적으로 처리하여 확률론적 지진취약성 분석을 수행한다. 응답 통계는 세기가 같은 지진파의 집단을 단계별로 scaling하는 stripe 방 법과 다양한 세기를 가진 지진파 집단을 선정하는 cloud방법을 적용하고 이 두 방법에 의한 분석결과의 차이를 비교한다. 한계 상태에는 교각의 휨변형과 교좌장치의 변위를 기준으로 산정한 다단계 한계상태를 적용하고, 여러 가지 한계상태를 취합한 시스템 취약성을 도출한다. 지진응답의 통계적 처리 방법과 교량의 손상 정의가 지진취약성 곡선에 주는 영향을 고찰한다.

최근 발생한 경주 및 포항 지진은 고주파 영역의 성분이 많이 포함된 지진파로 구조적 요소 뿐만아니라 비구조적 요소에 피해가 많이 발생하였다. 비구조적 요소 중 전기 캐비닛은 발전소의 발전 시스템 컨트롤러를 보관하는 함으로써 전기 캐 비닛의 피해는 안정적인 에너지 공급의 중단과 화재 등의 2차적인 피해로 확장될 수 있다. 따라서 본 연구에서는 전기 캐비닛- 앵커 시스템의 유한요소 모델을 구축하고 검증하여 세계 각지에서 발생한 지진파 적용을 통한 지진 취약도 평가를 수행하고자 한다. 전기 캐비닛의 유한요소 모델의 경우 공진탐색 결과의 타겟 주파수와 약 1%의 오차가 발생하였으며 선설치 앵커의 유한 요소 모델은 실험결과와 비교하였을 때 초기 강성 및 최대 하중점이 잘 일치하는 것으로 나타났다. 0.2g, 0.5g, 0.8g, 1.2g로 스케 일을 변화시켜 시간이력해석을 수행하였으며 해석결과를 바탕으로 확률론적 안전성 평가인 지진 취약도 평가를 수행하였다. 0.2g 스케일의 시간이력 해석결과 경주 지진을 적용하였을 때 앵커에서 발생한 응력은 280.15MPa로 가장 크게 발생하였으며 고 주파 지진에 민감하게 반응하는 것으로 나타났다. 앵커의 응력을 한계상태로 지진취약도 분석 시 0.2g와 0.5g 사이에서 기울기 가 급격히 변하였으며 캐비닛 최상단의 변위를 한계상태로 지진 취약도 분석 시 Z축 변위 보다 X축 변위에 대해 민감하게 반응하는 것으로 나타났다

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.

화력발전소 구조물 중 하나인 보일러 강구조물은 물탱크가 올라가게 되는 중요한 설비지만 그 중요성이 비해 지진에 대한 안전성 평가에 대한 연구가 미비하다. 본 연구에서는 취약도 곡선을 도출하고자 16개의 지진파에 12개의 PGA값을 선정하고 포 항지진을 포함해 총 200회의 동적 비선형 해석을 수행하였다. 강재의 인장, 압축응력과 강구조물의 상대변위를 측정하였다. 강재 재료적 특성의 경우 변형은 발생하였으나 파괴는 발생하지 않았고, 상대변위의 경우 한계점에 못 미치는 변위가 발생하였다. 취약도 곡선 도출결과 국내의 지진구역 구분 및 지역계수를 기준으로 강재의 재료적 변형(400MPa)에서는 인장이 38%, 압축이 62.5%로 변형이 발생하였고, 상대변위는 0%의 확률로 한계점을 넘었다. 이러한 보일러 강구조물에 대한 취약도 곡선은 대상구조물에 대한 한 계상태를 판별하는 정량적 근거와 지진에 대한 안전설계시 활용될 수 있다.

Seismic performance of ordinary reinforced concrete shear wall systems commonly used in high-rise residential buildings is evaluated. Three types of shear walls exceeding 60m in height are designed by performance-based seismic design. Then, incremental dynamic analysis is performed collapse probability is assessed in accordance with the procedure of FEMA P695. As a result, story drift, plastic rotation, and compressive strain are observed to be major failure modes, but shear failure occur little. Collapse probability and collapse margin ratio of performance groups do not meet requirement of FEMA P695. It is observed that critical wall elements fail due to excessive compressive strain. Therefore, the compressive strain of concrete at the boundary area of the shear wall needs to be evaluated with more conservative acceptance criteria.

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.

A total of 594 reservoirs (17%), which are managed by KRC, equipped with earthquake-resistant facilities whereas remaining ones did not. In addition, reservoirs were placed without the effect of geological structures (i.e., fault and lineament). Therefore, development on technique for alleviating the potential hazards by natural disasters along faults and lineaments has required. In addition, an effective reinforcement guideline related to the geological vulnerabilities around reservoirs has required. The final goal of this study is to suggest the effective maintenance for the safety of earth fill dams. A radius 2 km, based on the center of the reservoir in the study area was set as the range of vulnerability impacts of each reservoir. Seismic design, precise safety diagnosis, seismic influence and geological structure were analyzed for the influence range of each reservoir. To classify the vulnerability of geological disasters according to the fault distribution around the reservoir, evaluation index of seismic performance, precise safety diagnosis, seismic influence and geological structure were also developed for each reservoir, which were a component of the vulnerability assessment of geological disasters. As a result, the reservoir with the highest vulnerability to geological disasters in the pilot district was analyzed as Kidong reservoir with an evaluation index of 0.364. Within the radius of 100km from the epicenter of the Pohang earthquake, the number of agricultural infrastructure facilities subject to urgent inspections were 1,180 including reservoirs, pumping stations and intakes. Four reservoirs were directly damaged by earthquake among 724 agricultural reservoirs. As a result of the precise inspection and electrical resistivity survey of the reservoir after the earthquake, it was reported that cracks on the crest of reservoirs were not a cause of concern. However, we are constantly monitoring the safety of agricultural facilities by Pohang aftershocks.

In recent years, the number of earthquakes has increased worldwide. There has been an extreme increase on the Korea Peninsula, which is considered a safety zone for earthquakes. In particular, in the event of earthquakes, most structures on the Korea Peninsula are severely damaged, because most are not designed to withstand them. Damage to and destruction of civil structures, such as bridges, nuclear facilities, and dams, is worse than that of other structures. It is necessary to evaluate and predict the extent of damage by earthquake magnitude, as the magnitude of earthquakes is increasing as well as the frequency. A major feature of the occurrence of earthquakes is uncertainty. For this reason, it is necessary to adopt a stochastic approach, and studies using this approach are increasing. However, although there have been several studies on bridges and nuclear facilities, there have been few studies on probabilistic seismic risk evaluation for multi-functional weirs. Thus, this study presents 3D multi-functional weirs and performs a time history analysis by using LS-DYNA, a general structure analysis program. Probabilistic seismic fragility assessment is conducted by Monte Carlo simulation.

The friction pendulum system(FPS) is a kind of seismic isolation devices for isolating structures from an earthquake. To analyze the effect of friction materials used in the friction pendulum system, fragility analysis of LNG tank with seismic isolation system was conducted. In this study, titanium dioxide(TiO2) nanoparticles were incorporated into polyvinylidene fluoride(PVDF) matrix to produce friction materials attached to the FPS. The base moment of the concrete outer tank and the acceleration of the structure were evaluated from different mixing ratios of constituents for the friction materials. The seismic fragility curves were developed based on two types of limit state. It is confirmed that evaluation of combined fragility curves with several limit states can be applied to select the optimum friction material satisfying the required performance of the FPS for various infrastructure.

Many studies are conducted in several fields for fragility analysis of structures or elements which is a probabilistic seismic safety analysis in consideration with uncertainty of seismic loading. It is hard to directly conduct fragility analysis for an infrastructure with social importance due to its size. Therefore, a fragility analysis for an infrastructure mainly conducted in element level or conducted with scaled model built in accordance with similarity law. In this article, fragility analysis for prototype and scaled model of reinforced concrete column was conducted with numerical models which had been updated by the results of shaking table test and pseudo dynamic test. As a result, response stress from the numerical analysis result of prototype model was higher than that from scaled model due to different stiffness ratios between steel and concrete. However, the probability of failure for scaled model was higher than that for prototype model because failure criteria for scaled model was down due to similarity law. Also it was evaluated that probability of failure by using log normal standard deviation of response stresses by spectrum matched accelerograms was more reliable than probability of failure by using existing coefficient of variation normally used.

In this study, refined finite element (FE) analyses intended to evaluate the capacity of the existing water purification plant structures against seismic force are conducted with an aim to predict possibility generating tension crack and compression crushing. The FE models for three types of main plant structures were constructed to take ground condition, boundary condition, and water interaction into consideration for advanced simulation. The nonlinear dynamic analyses were performed by using ground motion data which have been used for seismic design. Both compression crushing and tention crack, which are distributed over concrete plant structures during peak ground acceleration (PGA), are investigated by analyzing failure possibility controlled with the strain limits. After observing FE analysis results, it is possible to predict tenstion cracking which can be found at some parts of the main structure.

The Korean peninsula has known as a minor-to-moderate seismic region. However, some recent studies had shown that the maximum possible earthquake magnitude in the region is approximately 6.3-6.5. Therefore, a seismic vulnerability assessment of the existing infrastructures considering ground motions in Korea is necessary. In this study, we developed seismic fragility curves for a continuous steel box girder bridge and two typical transmission towers, in which a set of seven artificial and natural ground motions recorded in South Korea is used. A finite element simulation framework, OpenSees, is utilized to perform nonlinear time history analyses of the bridge and a commercial software, SAP2000, is used to perform time history analyses of the transmission towers. The fragility curves based on Korean ground motions were then compared with the fragility curves generated using worldwide ground motions to evaluate the effect of the two ground motion groups on the seismic fragility curves of the structures. The results show that both non-isolated and base-isolated bridges are less vulnerable to the Korean ground motions than to worldwide earthquakes. Similarly to the bridge case, the transmission towers are safer during Korean motions than that under worldwide earthquakes in terms of fragility functions.

지진시 사회 인프라시설물의 피해는 시설물 자체의 피해보다 사회 전반에 걸친 2차 피해를 야기한다. 그 중, 지하 공동구 구조물은 통신, 가스, 전기 등 사회의 라이프라인에 해당하여 지진에 대한 취약성을 정확히 평가하여야 할 필요가 있다. 따 라서, 본 연구에서는 지하 공동구의 지진 발생 지반가속도에 따른 파괴가능성을 평가하였다. 평가를 위한 입력지반운동은 해 외 실측 지진데이터와 한반도에서 발생가능한 인공지진파를 차용하였으며, 지진해석 방법은 응답변위법과 시간이력해석법 을 사용하였다. 파괴여부를 판별하는 한계상태는 휨모멘트와 전단 파괴를 바탕으로 하였다. 취약도 함수 도출을 위한 방법은 최우도법이 사용되었으며, 그 분포함수는 대수정규분포로 가정하였다. 이는 지진시 지하 공동구 시설물의 피해 평가는 물론 지하 공동구 시설물의 내진설계를 위한 기초자료로 활용될 수 있다.

Observations of the damages to high-rise reinforced concrete (RC) wall building structures caused by by recent earthquakes in Chile (Mw 8.8, February 2010) and New Zealand (February 2011, ML 6.3) have generally exceeded expectations. Firstly, this study estimated the seismic damage levels of 15-story RC box-type wall building structures using the analytical models calibrated by the results of a shaking table test on a 1:5 scale 10-story RC box-type wall building model. Then, the seismic fragility analysis of the prototype model was conducted by using the SAC/FEMA method and the incremental dynamic analysis (IDA). To compensate for the uncertainties and variability of ground motion and its impacts on the prototype model, in the SAC/FEMA method, a total of 61 ground motion records were selected from 20 earthquakes, with a magnitude ranging from 5.9 to 8.8 and an epicentral distance ranging from 5 to 105km. In the IDA, a total of 11 ground motion records were used based on the uniform hazard response spectrum representing a return period of 2,475 years. As a result, the probabilities that the limits of the serviceability, damage control, and collapse prevention would be exceeded were as follows: from the SAC/FEMA method: 79%, 0.3%, and 0%, respectively; and from the IDA: 57%, 1.7%, and 0%, respectively.

If scour is occurred at shallow foundation of bridge, seismic performance of the bridge will be reduced. In order to evaluate accurate seismic response of bridge according to scour depths, modeling of foundation reflecting scour effect is important. In this study, taking into account the effect of the reduction in embedment depth of the shallow foundation by scouring, the soil around the foundation is modelled as an equivalent soil spring with various stiffness. Seismic fragility analyses for 3 types of bridges subjected to 4 types of ground motions classified into Site Class A, B, C, D are evaluated according to several scour depths. From the fragility analysis results, it can be observed that the deeper the scour depth, the higher probability of exceeding damage states. Also, seismic failure probability of asymmetric bridge is higher than that of symmetric bridge.

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.

원자력발전소에는 전력생산과 안전과 관련된 수많은 기기들이 존재하고 있다. 기본적으로 원자력발전소의 구조물과 기기는 지진시 탄성거동올 목표로 안전율을 매우 높게 적용하여 설계해 왔다. 그러나 최근 발생한 지진의 규모가 증가함에 따라 설계수준을 초과한 지진에 대한 기기의 안전성을 재평가할 필요가 있다. 본 연구에서는 구조물의 비선형 거동에 의한 층응답을 분석하였고, 비선형해석에 의한 구조물의 비탄성구조응답계수를 재평가하였다. 기기의 지진취약도 평가시 구조물의 비탄성구조응답이 어떤 영향을 주는지 분석하기 위하여 재평가된 구조물의 비탄성구조응답계수와 기존에 사용되어온 구조물 비탄성구조응답계수를 적용하여 지진취약도 평가를 수행하였다. 해석결과에 따르면 비탄성구조응답계수는 기기의 고유진동수, 기기의 위치 그리고 구조물의 동특성에 따라 영향을 받는 것으로 나타났다.

도시기반 라이프라인은 지진발생시 시설물의 붕괴뿐만 아니라 붕괴로 인한 도시기능 마비, 대형화재와 같은 2차 피해를 동반하여 막대한 사회·경제적 손실을 야기할 것으로 예측된다. 이에 대한 대비책으로 국내에서는 지진재해대응시스템을 운영 중이며, 지진재해대응시스템은 각 시설물별 지진취약도 모델을 통해서 시설물의 파괴확률을 산정하고, 지진재해 정도를 평가한다. 따라서 본 논문에서는 국내 지반특성을 고려하여 도시기반 라이프라인 시설물 중 매설가스배관의 시간이력 해석을 수행하였고, 확률론적인 해석방법인 최우도추정법을 이용하여 지진취약도 모델을 개발하였다. 해석모델은 국내 대표도시인 서울지역에 매설된 고압관과 중압관으로 선정하였으며, 지반의 모델링은 Winkler foundation 모델을 이용하였다. 또한 개발된 취약도 모델의 GIS 적용방안을 제시하였다.