원전 내 전기기기의 내진성능 평가는 안전성 확보에 매우 중요하다. 이 연구에서는 원전에 설치되는 전기기기의 동특성 및 현장조사 결과를 참고하여 모형 캐비닛과 앵커기초를 설계 및 제작하였다. 제작된 모형 캐비닛을 대상으로 진동대실험을 수행하였다. 실험 결과를 바탕으로 유한요소모델을 작성하고 지진응답해석을 수행하였다. 입력지진동이 커짐에 따른 실험 및 해석 결과를 비교하여 모형 캐비닛의 지진거동특성을 분석하였다. 두 결과에 대한 모형 캐비닛의 지진거동은 다르며 내진성능에 큰 차이가 발생할 수 있다. 따라서 캐비닛과 콘크리트 기초 사이의 상호작용을 고려할 수 없는 경우 캐비닛의 지진거동 특성은 실험적으로 평가하는 것이 적절할 것으로 판단하였다.

In the seismic evaluation of underground utility tunnels, selecting an analytical method is critical to estimating reasonable seismic responses. In simplified pseudo-static analysis methods widely applied to typical seismic design and evaluation of underground tunnels in practice, it is essential to check whether the methods provide valid results for cut-and-cover tunnels buried in shallow to medium depth. The differences between the two simplified pseudo-static methods are discussed in this study, and the analysis results are compared to those obtained from FLAC models. In addition to the analysis methods, seismic site classification, overburden soil depth, and sectional configuration are considered variables to examine their effects on the seismic response of underground utility tunnels. Based on the analysis results, the characteristics derived from the concepts and details of each simplified model are discussed. Also, general observations are made for the application of simplified analysis methods.

수소는 연소 과정에서 산소와 반응하여 물과 열만을 생성하며 공해 물질이 배출하지 않아 깨끗한 에너지원으로 간주된다. 이러한 특징으로 산업 활동으로 비롯된 대기 오염, 이상 기후 문제 등을 해결 하기 위한 대책안으로써 수소를 활용한 신재생에너지가 세계적으로 주목받고 있다. 이에 따라 선행 연 구에서는 수직형 탱크 구조의 취약부로 평가되는 지지부 단면 변화에 따른 영향성을 평가하기 위해 수소 생산 인프라 현장 조사를 수행한 바 있으며, 현장 조사 중에 현장 설치된 수소 탱크 강재 지지부 의 부식 문제를 확인하였다. 지지부의 부식은 구조물의 전체 강성을 감소시키며, 재난(지진)에 취약해 져 수소 저장 용기가 손상으로 인한 2차 피해로 이어질 수 있다. 이에 따라 본 연구는 선행 연구의 후속 연구로써 강재 지지부의 부식 문제를 개선하고자 고강도-저중량 재료인 CFRP(Carbon Fiber Reinforced Polymer)를 사용한 지지부를 개발하여 수치해석을 통해 CFRP 지지부의 내진 성능평가를 목적으로 한다. 해석에 사용된 수소 탱크는 크게 몸체, 지지부, 기초부, 앵커 볼트로 구성되어 있으며, 지지부는 높이 965mm, 75×75×9.5mm의 L형강 4개로 확인되었다. 지진 하중에 대한 동적 성능을 평가하기 위해 시간이력해석법이 사용되었으며, 적용 동적하중의 경우, ASCE의 ICC-ES에서 제시한 평가 기준에 따라 AC 156 Amplitude 100%의 인공 지진을 적용하였다. 해석 결과, CFRP 지지부와 강재 지지부 상단의 최대 변위가 각각 35.48, 32.54mm로 매우 유사한 것으로 나타났으며, Hashin Damage Criteria를 사용하여 CFRP 지지부의 최대 손상 지수를 측정한 결과 수지의 인장측에서 0.065로 확인되었다. 이는 기준 손상 지수 1 대비 매우 낮은 수준이며, 해석 결과를 종합했을 때 CFRP 지지부는 충분한 안전성을 보이는 것으로 판단된다.

The seismic separation joint is an important device that absorbs vibration displacement from earthquake shock and protects fire extinguishing pipes and various utility pipes. In this study, the mechanical behavior occurring in U-typed and V-typed seismic separation joint was analyzed according to the length of the bellows, the length of the elbow straight pipe, and the open angle. As a result, as the length of the bellows increased, the stress and natural frequency decreased. In addition, as the length of the elbow straight pipe increased, the stress tended to decrease in the case of forced displacement in the vertical direction. As the open angle increased, the stress in the case of forced displacement in the left and right directions increased.

본 연구에서는 수소 자원의 활용도가 높아짐에 따라 수소 저장 용기의 내진 성능을 평가하기 위해 수소 저장 시설을 방문하여 현장 조사를 수행하였다. 외관 조사 중, 수조 저장 용기의 지지부에서 부식이 진행됨을 확인하였고, 이에 대한 대책안 으로 내부식성 재료인 CFRP로 대체하여 성능을 평가, 검증하였다. 이를 위해 현장 조사 결과를 바탕으로 상용 유한요소해석 프 로그램인 ABAQUS를 사용하였으며, 해석 결과 CFRP로 제작된 수소 저장 용기의 지지부는 강재 대비 약 12배 이상 뛰어난 성 능을 보였다. Hashin Damage Criteria를 기반으로 CFRP 지지부의 안전성 검토를 수행한 결과 최대 손상 지수가 0.065로 확인되 었다. 기초부 콘크리트의 경우, 쪼갬 및 휨 인장 응력에 대한 안전성을 검토하였으며, 허용 강도 대비 7~36%의 안전도를 보였 다. 이를 근거로 CFRP를 수소 저장 용기의 지지부에 적용하는 것은 합리적이며, 뛰어난 경제성을 보인다. 다만, 이러한 결과는 수치 해석에 의하므로 실규모 지진동 모사 시험을 통해 해석 모델의 신뢰성을 보충할 필요가 있다.

This study performed the seismic response analysis of an LNG storage tank supported by a disconnected piled raft foundation (DPRF) with a load transfer platform (LTP). For this purpose, a precise analytical model with simultaneous consideration of Fluid-Structure Interaction (FSI) and Soil-Structure Interaction (SSI) was used. The effect of the LTP characteristics (thickness, stiffness) of the DPRF system on the seismic response of the superstructure (inner and outer tanks) and piles was analyzed. The analytical results were compared with the response of the piled raft foundation (PRF) system. The following conclusions can be drawn from the numerical results: (1) The DPRF system has a smaller bending moment and axial force at the head of the pile than the PRF system, even if the thickness and stiffness of the LTP change; (2) The DPRF system has a slight stiffness of the LTP and the superstructure member force can increase with increasing thickness. This is because as the stiffness of the LTP decreases and the thickness increases, the natural frequency of the LTP becomes closer to the natural frequency of the superstructure, which may affect the response of the superstructure. Therefore, when applying the DPRF system, it is recommended that the sensitivity analysis of the seismic response to the thickness and stiffness of the LTP must be performed.

지진취약도를 산정하기 위해서는 목표 부지의 특성을 제대로 표현할 수 있는 입력 지진파의 산정이 중요하다. 본 논문에서는 국내 외 강진 및 중‧약진 지역에서의 입력 지진파에 대한 단자유도 모델의 지진취약도를 분석하였다. 분석을 위한 첫 번째 단계로, 국외 강 진 기록 중 근/원거리에서 측정한 2개의 입력 지진파 세트와 국내 중·약진 지역 특성에 적합한 입력 지진파 2개의 세트, 총 4개의 입력 지진파 세트를 선정하였다. 대상 구조물로는 3가지 고유주기에 대한 비선형 단자유도 모델을 적용하였고, 취약도 분석을 위해 증분동 적해석을 이용하였다. 또한, 4가지 손상 상태를 정의하고, 손상 상태 각각에 대해 4가지 입력 지진파 세트의 고유주기별 지진취약도 결과를 제시하였다.

Recently, the occurrence frequency of earthquake has increased in Korea, and the interests for seismic reinforcement of existing school buildings have been raised. To this end, the seismic performance evaluations for school buildings that did not accomplish the seismic design are required. In particular, this study checks the eigenvalue analysis, pushover curves, maximum base shears, performance points and story drift ratios, and then analyzes the seismic performance characteristics according to bracing configuration of steel frame system reinforcement. Also, this study presents the practical field application methods through the comparison of analysis results for the seismic performance characteristics.

In this study, the seismic response characteristics of the three analysis model with or without TMD were investigated to find out the effective dome shape. The three analysis models are rib type, lattice type and geodesic type dome structure composed of space frame. The maximum vertical and horizontal displacements were evaluated at 1/4 point of the span by applying the resonance harmonic load and historical earthquake loads (El Centro, Kobe, Northridge earthquakes). The study of the effective TMD installation position for the dome structure shows that seismic response control was effective when eight TMDs were installed in all types of analysis model. The investigation of the efficiency of TMD according to dome shape presents that lattice dome and geodesic dome show excellent control performance, while rib dome shows different control performance depending on the historical seismic loads. Therefore, lattice and geodesic types are desirable for seismic response reduction using TMD compared to rib type.

In the case of dry storage facilities, slipping of the cask or tip-over are dangerous phenomena. For this reason, in dry storage facilities, measures against slipping and tip-over or related safety evaluations are important. Accidental conditions that can cause cask slippage and tip-over in dry storage facilities include natural phenomena such as floods, tornadoes, tsunamis, typhoons, earthquakes, and artificial phenomena such as airplane crashes. However, among natural phenomena, earthquakes are the most important natural phenomenon that causes tip-over. Also, many people had the stereotype that Korea is an earthquake-safe zone before 2016. However, earthquakes become a major disaster in Korea due to the 2016 Gyeongju earthquake and the 2017 Pohang earthquake, followed by the Goesan earthquake in October 2022. In this paper, seismic analysis was performed based on dry storage facilities including multiple casks. Design variables for the construction of an analysis model for dry storage facilities were investigated, and seismic analysis was performed. To evaluate tip-over accident during earthquake, seismic load was used from 0.2 g PGA to 0.8 g PGA and these earthquakes were followed Design Response Spectrum (DRS) in RG 1.60. The friction coefficient of concrete pad was used from 0.2 to 1.0. As a result of the analysis, tip-over accident could not find in the analysis from 0.2 g to 0.6 g. However, tip-over was appeared at friction coefficients of 0.8 and 1.0 at 0.8 g PGA. Tip-over angular velocity of cask was derived by seismic analysis and was compared with formula and tip-over analysis results. As a result, a generalized dry storage facility analysis model was proposed, and dry storage facility safety evaluation was conducted through seismic analysis. Also, tip-over angular velocity was derived using seismic analysis for tip-over analysis.

Seismic fragility curves play a crucial role in assessing potential seismic losses and predicting structural damage caused by earthquakes. This study compares non-sampling-based methods of seismic fragility curve derivation, particularly the probabilistic seismic demand model (PSDM) and finite element reliability analysis (FERA), both of which require employing sophisticated finite element analysis to evaluate and predict structural damage caused by earthquakes. In this study, a three-dimensional finite element model of API 5L X65, a buried gas pipeline widely used in Korea, is constructed to derive seismic fragility curves. Its seismic vulnerability is assessed using nonlinear time-history analysis. PSDM and a FERA are employed to derive seismic fragility curves for comparison purposes, and the results are verified through a comparison with those from the Monte Carlo Simulation (MCS). It is observed that the fragility curves obtained from PSDM are relatively conservative, which is attributed to the assumption introduced to consider the uncertainty factors. In addition, this study provides a comprehensive comparison of seismic fragility curve derivation methods based on sophisticated finite element analysis, which may contribute to developing more accurate and efficient seismic fragility analysis.

본 연구에서는 마찰모델에 따라 다른 마찰진자시스템(FPS)이 적용된 교량의 성능을 비교･분석하기 위해 구조해석을 수행하였다. 마찰해석모델 별 성능을 분석하기 위해 PVDF/MgO 마찰재의 마찰계수를 활용하여 쿨롱 마찰모델과 속도 의존 마찰모델을 구축했다. 쿨롱 마찰모델은 마찰속도와 관계없이 단일 마찰계수를 사용하며, 속도 의존 마찰모델은 마찰속도에 따른 마찰계수의 변화를 반영하 는 마찰모델이다. 지진해석으로 비선형 시간 이력 해석과 지진 취약도 해석을 수행하여 구조물의 응답을 확인하였다. 마찰모델에 따 른 바닥판과 교각의 지진 응답을 활용해 면진된 교량의 성능을 분석하였으며, 면진된 교량의 성능을 효과적으로 평가할 수 있는 마찰 모델을 분석했다.

완공된 건물과 달리 시공 중인 건물은 설계단계와 다른 하중 작용 및 콘크리트 강도 미발현 등 다양한 요인에 의해 설계단계에서 검 토한 하중을 초과하는 하중이 작용하여 건물의 안전성에 문제가 생길 위험이 있다. 또한 시공 중인 건물에 지진이 발생할 경우 더 큰 피해가 발생할 가능성이 있다. 따라서 이 연구는 전형적인 다양한 규모의 5층, 15층, 25층, 60층 예제모델을 작성하고 골조완성도에 따 른 시공단계 모델을 통해 시공 중인 건물의 지진하중의 영향을 분석하였다. 시공 중인 건물의 시공기간은 완공단계 이후의 사용기간 에 비해 매우 짧으므로 설계단계와 동등한 수준의 지진을 적용하는 것은 과도한 하중이 적용될 수 있으므로 시공단계 모델에 재현주 기 50~2,400년의 지진을 적용하여 지진하중을 검토하고 부재단면성능을 분석하였다. 그 결과 설계단계를 초과하는 하중의 여부 및 구조적 안전성 확보가 가능한 수준의 지진재현주기를 검토할 수 있었다. 또한 각 예제모델의 시공기간을 가정하여 시공기간에 따른 지진재현주기를 선정하고 선정한 재현주기의 설계 적절성을 확인하였다.

Structural vibration induced by earthquake hazards is one of the most significant concerns in structure performance-based design. Structural hazards evoked from seismic events must be properly identified to make buildings resilient enough to withstand extreme earthquake loadings. To investigate the effects of combined earthquake-resistant systems, shear walls and five types of dampers are incorporated in nineteen structural models by altering their arrangements. All the building models were developed as per ACI 318-14 and ASCE 7-16. Seismic fragility curves were developed from the incremental dynamic analyses (IDA) performed by using seven sets of ground motions, and eventually, by following FEMA P695 provisions, the collapse margin ratio (CMR) was computed from the collapse curves. It is evident from the results that the seismic performance of the proposed combined shear wall-damper system is significantly better than the models equipped with shear walls only. The scrutinized dual seismic resisting system is expected to be applied practically to ensure a multi-level shield for tall structures in high seismic risk zones.

The recent increase in earthquake activities has highlighted the importance of seismic performance evaluation for civil infrastructures. In particular, the container crane essential to maintaining the national logistics system with port operation requires an exact evaluation of its seismic response. Thus, this study aims to assess the seismic vulnerability of container cranes considering their seismic characteristics. The seismic response of the container crane should account for the structural members’ yielding and buckling, as well as the crane wheel’s uplifting derailment in operation. The crane’s yielding and buckling limit states were defined using the stress of crane members based on the load and displacement curve obtained from nonlinear static analysis. The derailment limit state was based on the height of the rail, and nonlinear dynamic analysis was performed to obtain the seismic fragility curves considering defined limit states and seismic characteristics. The yield and derailment probabilities of the crane in the near-fault ground motion were approximately 1.5 to 4.7 and 2.8 to 6.8 times higher, respectively, than those in the far-fault ground motion.

In Korea, most nuclear power plants were designed based on the design response spectrum of Regulatory Guide 1.60 of the NRC. However, in the case of earthquakes occurring in the country, the characteristics of seismic motions in Korea and the design response spectrum differed. The seismic motion in Korea had a higher spectral acceleration in the high-frequency range compared to the design response spectrum. The seismic capacity may be reduced when evaluating the seismic performance of the equipment with high-frequency earthquakes compared with what is evaluated by the design response spectrum for the equipment with a high natural frequency. Therefore, EPRI proposed the inelastic energy absorption factor for the equipment anchorage. In this study, the seismic performance of welding anchorage was evaluated by considering domestic seismic characteristics and EPRI's inelastic energy absorption factor. In order to reflect the characteristics of domestic earthquakes, the uniform hazard response spectrum (UHRS) of Uljin was used. Moreover, the seismic performance of the equipment was evaluated with a design response spectrum of R.G.1.60 and a uniform hazard response spectrum (UHRS) as seismic inputs. As a result, it was confirmed that the seismic performance of the weld anchorage could be increased when the inelastic energy absorption factor is used. Also, a comparative analysis was performed on the seismic capacity of the anchorage of equipment by the welding and the extended bolt.

Existing reinforced concrete building structures constructed before 1988 have seismically-deficient reinforcing details, which can lead to the premature failure of the columns and beam-column joints. The premature failure was resulted from the inadequate bonding performance between the reinforcing bars and surrounding concrete on the main structural elements. This paper aims to quantify the bond-slip effect on the dynamic responses of reinforced concrete frame models using finite element analyses. The bond-slip behavior was modeled using an one-dimensional slide line model in LS-DYNA. The bond-slip models were varied with the bonding conditions and failure modes, and implemented to the well-validated finite element models. The dynamic responses of the frame models with the several bonding conditions were compared to the validated models reproducing the actual behavior. It verifies that the bond-slip effects significantly affected the dynamic responses of the reinforced concrete building structures.

Some Spent Fuel Pools (SFPs) will be full of Spent Nuclear Fuels (SNFs) within several years. Because of this reason, building interim storage facilities or permanent disposal facilities should be considered. These storage facilities are divided into wet storage facilities and dry storage facilities. Wet storage facility is a method of storing SNF in SFP to cool decay heat and shielding radiation, and dry storage facility is a method of storing SNF in a cask and placing on the ground or storage building. However, wet storage facilities have disadvantages in that operating costs are higher than that of dry storage facilities, and additional capacity expansion is difficult. Dry storage facilities have relatively low operating costs and are relatively easy to increase capacity when additional SNFs need to be stored. For this reason, since the 1990s, the number of cases of applying dry storage facilities has been increasing even abroad. Dry storage facilities are divided into indoor storage facilities and outdoor storage facilities, and outdoor storage facilities are mostly used to take advantage of dry storage facilities. In the case of outdoor storage facilities, the cask in which SNFs are stored is placed on a designed concrete pad. During this storage, the boring heat generated by SNFs cools into natural convection and the cask shields the radiation that SNFs generates. However, if an accident such as an earthquake occurs and the cask overturns during storage, there may be a risk of radiation leakage. Such a tip-over accident may be caused by the cask slipping due to the vibration of an earthquake, or by not supporting the cask properly due to a problem in the concrete pad. Therefore, in the case of outdoor dry storage facilities, it is necessary to evaluate the seismic safety of concrete pads. In this paper, various soil conditions were applied in the seismic analysis. Soil conditions were classified according to the shear wave velocity, and the shear wave velocity was classified according to the ground classification criteria according to the general seismic design (KDS 17 10 00). The concrete pad was designed with a size that 8 casks can be arranged at regular intervals, and 11# reinforcing bars were used for the design of the internal reinforcement of the concrete pad according to literature research. The cask was designed as a rigid body to shorten the analysis time. The soil to which the elastic model was applied was designed under the concrete pad, and infinite elements were applied to the sides and bottom of the soil. The effect on the concrete pad and cask by applying a seismic wave conforming to RG 1.60 to the bottom of the soil was analyzed with a finite element model.

In assessing the seismic safety of nuclear power plants, it is essential to analyze the structures using the observed ground motion. In particular, spatial variation in which the characteristics of the ground motion record differ may occur if the location is different within the site and even if the same earthquake is experienced. This study analyzed the spatial variation characteristics of the ground motion observed at the structure and site using the earthquake records measured at the Hamaoka nuclear power plant. Even if they were located on the same floor within the same unit, there was a difference in response depending on the location. In addition, amplification was observed in Unit 5 compared to other units, which was due to the rock layer having a slower shear wave velocity than the surrounding bedrock. Significant differences were also found in the records of the structure’s foundation and the free-field surface. Based on these results, the necessity of considering spatial variation in the observed records was suggested.