강진에 대한 다양한 비선형 거동을 하는 부재요소들로 이루어진 교량시스템의 현재까지의 일반적인 지진취약도 평가방법은 부재- 수준에서 평가하는 것이다. 본 연구의 목적 부재-수준의 지진취약도 평가결과로부터 구조시스템을 대표하는 시스템-수준의 지진취 약도 평가방법을 개발하는 것이다. 교량의 지진 거동을 일반적으로 교축방향과 교축직각방향으로 구분하기 때문에 본 연구에서도 시 스템-수준 지진취약도를 두 방향에 대하여 구분해 평가하였다. 길이 방향에 대한 부재-수준의 지진취약도평가는 교각, 교량받침, 충 돌, 교대, 낙교에 대하여 수행하였다. 교축직각 방향에 대해서는 충돌, 교대, 낙교의 손상이 영향을 주지 않으므로 부재-수준의 지진취 약도평가는 교각과 교량받침에 대하여만 수행하였다. 다양한 구조부재의 비선형모델을 이용한 지진해석은 OpenSEES 프로그램을 사용하여 수행하였다. 시스템-수준의 지진취약도는 부재-수준 사이의 손상이 직렬연결이라고 가정하고 평가하였다. 교각의 손상이 다른 부재-수준의 손상보다 시스템-수준의 지진취약도에 지배적인 영향을 주는 것을 알 수 있었다. 다시 말하면 가장 취약한 부재-수 준의 지진취약도가 시스템-수준의 지진취약도에 가장 지배적인 영향을 주는 것을 의미한다.

교량은 사용년한이 증가함에 따라 노후화로 인해 역학적인 성질과 구조적인 성능이 저하되고, 이로 인해서 강진 시에 내진성능이 저하된다. 교각과 교량받침에 대한 노후화를 몇 가지 단계로 정량화하여 해석모델에 반영하였고, 노후화된 교각과 교량받침에 대하 여 부재-수준의 지진취약도를 평가하였다. 교량 시스템의 파괴 메카니즘을 직렬시스템으로 가정하여, 부재-수준의 지진취약도 해석 결과로부터 시스템-수준의 지진취약도를 평가하는 방법을 제안하였다. 노후도에 취약한 부재인 교각과 교량받침에 대하여 5가지 정 량적인 노후도(0, 5, 10, 25, 40%)를 가정하여 부재-수준의 지진취약도를 평가하였고, 이 결과로부터 시스템-수준의 지진취약도 평가 를 수행하였다. 시스템-수준의 지진취약도는 교량받침 보다는 교각이 지배적인 영향을 줌을 알 수 있었다. 이는 보다 취약한 구조부재 의 지진취약도가 전체 교량시스템의 지진취약도에 지배적인 영향을 주는 것을 의미한다.

교량의 노후화는 다양한 원인에 기인하겠지만 겨울철에 제설용으로 살포하는 염화칼슘이 교량부재에 침투하여 부식을 유발하는 것이 대표적인 교량 노후화 원인중 하나라고 할 수 있다. 본 연구의 목적은 교량의 부식에 의한 노후화 정도를 정량화하고 이를 교량의 해석모델에 적용하여 노후화 정도에 따른 지진취약도 해석을 수행하고 노후화 정도와 지진취약도 곡선의 관계를 평가하는 것이다. 노후화 정도를 고려한 지진취약도 해석에 각 손상상태별로 한계값을 적절히 정의하는 것이 중요하다. 본 연구에서는 손상정도에 따른 변위 연성도 능력의 저하 특성에 관한 기존 연구결과를 활용하여 손상상태를 정의하였다. 세 가지 교량받침과 두 가지 교각 높이에 따른 예제 교량들의 지진취약도 해석으로부터 노후화 정도가 증가할수록 지진취약도가 증가하는 경향이 나타냄을 알 수 있다. 이러 한 노후화 정도에 따른 지진취약도의 차이는 손상상태가 경미, 보통, 심각, 붕괴의 상태로 갈수록 증가하는 경향을 나타낸다.

피암터널은 낙석방지시설 중 하나로 비교적 큰 낙석이 발생할 수 있는 급경사지 도로위에 건설된다. 일반적으로 피암터널은 약 200kJ에서 3,000kJ 까지의 낙석에너지에 저항할 수 있도록 설계된다. 기존 연구에서 이러한 피암터널의 효율성을 증대하기 위하여 콘크리트 충전강관(CFT, Concrete-Filled Tube)를 주구조체로 사용하는 신형식 피암터널을 제시하였다. CFT를 주구조체로 활용함으로서 급속시공이 가능하며 높은 하중저항 능력과 연성 또한 확보할 수 있는 장점이 있다. 하지만, 기존 연구에서는 선현 탄성 해석을 통하여 거동을 분석하여 한계를 가지고 있어 보다 실제적인 낙성하중을 고려한 3차원 유한요소해석을 통하여 제안된 피암터널의 거동을 분석할 필요가 있다. 본 연구에서는 먼저 제안된 피암터널 주구조체에 대한 실제 낙석하중을 포함한 3차원 유한요소해석을 개발하였다. 이후 최대 낙석에너지에 대한 제안된 피암터널 주구조체의 낙석 저항능력에 대하여 연구를 수행하였다.

현재 우리나라에서 운영 중인 교량 중 30년 이상 된 교량이 전체의 약 11%를 차지할 정도로 노후교량의 수가 증가하고 있다. 따라 서 교량의 노후화에 따른 영향을 고려한 내진성능 평가방법의 개발이 필요하다고 볼 수 있다. 예제 교량으로는 포트받침, 탄성고무받 침과 납-고무받침을 가진 3가지의 강합성 상자형 거더교를 선정하고, opensees 프로그램을 사용하여 구조해석모델을 작성하였다. 본 연구에서는 교량의 노후도를 교각의 주철근과 띠철근의 부식에 의한 면적의 감소로 반영하였다. 교각의 노후화 정도로는 5%, 10%, 25%, 50%의 4가지 조건을 사용하였다. 입력지진으로는 근거리 지진과 원거리 지진을 각각 40개씩 사용하였으며, 노후화 정도에 따른 예제교량의 교각에 대한 최대변위와 최대 전단력 응답을 구하여 비교하였다. 노후도가 증가할수록 힘-변위 관계에서 교각의 강도 저하가 발생함을 알 수 있으며, 이로 인하여 교각의 변위응답이 증가함을 알 수 있다. 교각의 노후도에 따른 변위응답과 전단저항능력의 영향을 분석하기 위하여 변위비(Dratio)와 전단력비(Fratio)를 정의하여 평가하였다. 예제교량의 고유주기가 길어질수록 노후도에 따른 변위비(Dratio)의 증가가 크게 나타남을 알 수 있으며, 전단력비(Fratio)의 감소 경향은 작게 나타남을 알 수 있다.

변전소 구조물 내부에 설치되는 전력설비의 내진설계 시 사용되는 변수인 가속도 증폭계수는 미국, 일본과 국내의 변전소 내진설 계기준에서 제시되어 있다. 국내 설계기준에 제시된 가속도 증폭계수는 미국, 일본의 설계기준에서 제시된 계수와는 달리 변전소 구조물의 층수가 4층 이상일 경우에는 동적해석을 수행하여 가속도 증폭계수를 구하게 되어 있다. 국내의 변전소 구조물은 대부분 층수가 4~5층이므로 기존의 가속도 증폭계수는 실제 변전소 구조물에 적용하기에 미흡한 상황이다. 국내 변전소 구조물 형식에 적합한 가속도 증폭계수를 제시하기 위하여 대표적인 7가지 구조형식의 변전소 구조물에 대하여 가속도 증폭계수를 평가하였다. 가속도증폭 계수는 변전소 구조물에 대하여 원거리 지진과 근거리 지진을 사용하여 내부-구조물 응답스펙트럼을 작성하여 이로부터 평가하였다. 미국, 일본 전력설비 내진설계 기준에 따른 각각의 가속도 증폭계수 αj, αA는 근거리 및 원거리 지진을 사용한 동적 해석으로 구한 가 속도 증폭계수에 비하여 다소 과대평가하는 경향이 있다.

The number of aged bridges is increasing so that bridges over 30 years old account for about 11% of all bridges. Consequently, the development of a seismic performance evaluation method that considers the effects of ageing is essential for a seismic retrofitting process for improvement of the seismic safety of existing old bridges. Assessment of the damage situation of bridges after the recent earthquakes in Korea has been limited to the bearings, anchor, and concrete mortar on piers. The purpose of this study is to evaluate the seismic responses of PSC box girder bridges by considering the ageing effect of rubber bearings (RBs) and lead-rubber bearings (LRBs). The modification factor proposed by AASHTO is used to take into account the ageing effect in the bearings. PSC box girder bridges with RBs and LRBs were 3D modeled and analyzed with the OpenSEES program. In order to evaluate the ageing effect of RBs and LRBs, 40 near fault and 40 far field records were used as the input earthquakes. When considering the effect of ageing, the displacement responses and shear forces of bridge bearings (RBs and LRBs) were found to increase mostly under the analytical conditions. It was shown that the effect of ageing is greater in the case of RBs than in the case of LRBs.

The tendency to use a probabilistic design method rather than a deterministic design method for the design of nuclear power plants (NPPs) will increase because their safety should be considered and strictly controlled in relation to various causes of damage. The distance between a seismically isolated NPP structure and a moat wall is called the clearance to stop. The clearance to stop is obtained from the 90th percentile displacement response of a seismically isolated NPP subject to a beyond design basis earthquake (BDBE) in the probabilistic design method. The purpose of this study is to analyze the effects of heating and buckling effects on the 90th percentile displacement response of a lead-rubber bearing (LRB) subject to a BDBE. The analysis results show that considering the heating and buckling effects to estimate the clearance to stop is conservative in the evaluation of the 90th percentile displacement response. If these two effects are not taken into account in the calculation of the clearance to stop, the underestimation of the clearance to stop causes unexpected damage because of an increase in the collision probability between the moat wall and the seismically isolated NPP.

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.

In order to modeling seismic isolation system such as lead-rubber bearing (LRB), bilinear model is widely used by many researchers. In general, an actual force-displacement relationship for LRB has a smooth hysteretic shape. So, Bouc-Wen model with smooth hysteretic shape represents more accurately actual hysteretic shape than bilinear model. In this study, seismic responses for seismically isolated nuclear power plant (NPP) with LRB modelled by Bouc-Wen and bilinear models are compared with those of NPP without seismic isolation system. To evaluate effect of earthquake characteristics for seismic responses of NPP isolated by LRB, 5 different site class earthquakes distinguished by Geomatrix 3rd Letter Site Classification and artificially generated earthquakes corresponding to standard design spectrum by Reg. Guide 1.60 are used as input earthquakes. From the seismic response results of seismically isolated NPP, it can be observed that maximum displacements of seismic isolation modelled by Bouc-Wen model are larger than those by bilinear model. Seismic responses of NPP with LRB is significantly reduced than those without LRB. This reduction effect for seismic responses of NPP subjected to Site A (rock) earthquakes is larger than that to Site E (soft soil) earthquakes.

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.

The lead-rubber bearing (LRB) dissipates seismic energy through plastic deformation of lead core. Under large-displacement cyclic motion, the temperature increases in the lead core. The shear strength of a lead–rubber bearing is reduced due to the heating effect of the lead core. In this study, the seismic responses such as displacement increasing, shear strength and vertical stiffness degradations of LRB due to the heating effect are evaluated for design basis earthquake (DBE) and beyond design basis earthquake (150% DBE, 167% DBE, 200% DBE).

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.

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.

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.

In order to increase the seismic safety of nuclear power plant (NPP) structures in high seismicity regions, seismic isolation techniques can be adapted to NPP structures. In this paper, the applicability of multi-step analysis of seismically isolated NPP containment structures with lead-rubber bearings (LRB) is evaluated. The floor response spectrum of NPP containment structures with equivalent linear LRB and nonlinear LRB are compared. In addition, the force-displacement relationships for equivalent linear LRB and nonlinear LRB are compared.