This study reviews concepts, theories and formulas included in standards on soil-structure interaction and also shows practical example of application for engineers. Real structures are 3 dimensional and multi degree of freedom but they are often idealized to single degree of freedom for convenience. In this study, detailed procedures to calculate soil spring constants and damping coefficients and method to model soil-structure system are explained. Additionally, case studies to judge fixed base condition and evaluation of applicability of simple analysis method based on response spectra are performed.

The boundary reaction method(BRM) is a substructure time domain method, it removes global iterations between frequency and time domain analyses commonly required in the hybrid approaches, so that it operates as a two-step uncoupled method. The BRM offers a two-step method as follows: (1) the calculation of boundary reaction forces in the frequency domain on an interface of linear and nonlinear regions, (2) solving the wave radiation problem subjected to the boundary reaction forces in the time domain. In the time domain analysis, the near-field soil is modeled to simulate the wave radiation problem. This paper evaluates the performance of the BRM according to modeling extent of near-field soil for the nonlinear SSI analysis of base-isolated NPP structure. For this purpose, parametric studies are performed using equivalent linear SSI problems. The accuracy of the BRM solution is evaluated by comparing the BRM solution with that of conventional SSI seismic technique. The numerical results show that the soil condition affects the modeling range of near-field soil for the BRM analysis as well as the size of the basemat. Finally, the BRM is applied for the nonlinear SSI analysis of a base-isolated NPP structure to demonstrate the accuracy and effectiveness of the method.

This study intends to evaluate the conservativeness of the fixed-base analysis as compared to the soil-structure interaction (SSI) analysis for the seismically isolated model of a nuclear power plant in Korea. To that goal, the boundary reaction method (BRM), combining frequency-domain and time-domain analyses in a twofold process, is adopted for the SSI analysis considering the nonlinearity of the seismic base isolation. The program KIESSI-3D is used for computing the reaction forces in the frequency domain and the program MIDAS/Civil is applied for the nonlinear time-domain analysis. The BRM numerical model is verified by comparing the results of the frequency-domain analysis and time-domain analysis for the soil-structure system with an equivalent linear base isolation model. Moreover, the displacement response of the base isolation and the horizontal response at the top of the structure obtained by the nonlinear SSI analysis using BRM are compared with those obtained by the fixed-base analysis. The comparison reveals that the fixed-base analysis provides conservative peak deformation for the base isolation but is not particularly conservative in term of the floor response spectrum of the superstructure.

Currently, researches are being actively conducted in assessing seismic performance of nuclear facilities in USA and Europe. In particular, applying this technique of assessing seismic performance to design of isolation systems in nuclear power plants is being performed and then ASCE 4 Draft (2013) is being revised accordingly in the United States. In order to satisfy the probabilistic performance objectives described by seismic responses with certain confidence levels (ASCE 43, 2005), the probability distributions of these responses have to be defined. What is the minimum number of input ground-motions to obtain the probability distribution precise enough to represent the unknown actual distribution? Theoretical basis, for how to determine the minimum number of input ground-motions for given a logarithmic standard deviation to approximate the unknown actual median of the log-normal distribution within a range of error at a certain level of confidence, is introduced by Huang et al. (2008). However, the relationship between the level of confidence and the range of error is not stated in the previous study. In this paper, based on careful reviews on the previous work, the relationship between the level of confidence and the range of error is logically and explicitly stated. Furthermore, this relationship is also applied to derive the minimum number of input ground-motions in order to approximate the unknown actual logarithmic standard deviation. Several recommendations are made for determining the minimum number of input ground-motions in probabilistic assessment on seismic performance of facilities in nuclear power plants.

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.

An Emergency Diesel Generator (EDG) installed in a nuclear power plant is the primary power source, supplying AC power to Class 1E power systems when the main turbine generator and offsite power source are not available. Thus, reliability of the EGD is essential for plant safety and availability. In this paper, the EDG is selected for a Long Term Asset Management (LTAM) strategy and the results are summarized briefly. The LTAM strategy is intended to provide an effective long-term planning tool for minimizing unplanned capability loss and then optimizing maintenance programs and capital investments consistent with plant safety and an identified plant operating strategy. Such an operating strategy might include license renewal or retaining the option for license renewal.

지진 발생시 원자력 발전소의 안전성을 평가하기 위해 수행되는 확률론적 지진 안전성평가를 위해서는 원전의 기기별로 지진 수준에 따른 파괴확률로서 표현되는 지진취약도 평가가 필요하다. 지진취약도 평가를 위해서는 대상 기기의 설계정보와 함께 실제 설치 상태에 대한 현장조사 등을 통해 예상되는 파손모드를 결정이 필요하며 주요 변수에 대한 불확실성 및 임의성 등 변동성 요인을 반영하여 결정된다. 본 연구에서는 구조적 파손이 지배하는 경우에 대하여 각 변수별로 변동성 요인을 도출하고 분산도 반영에 따른 지진취약도 영향 요인을 분석하고자 한다.

Most of equipment in nuclear power plants (NPPs) is anchored to the concrete structure or other components with concrete anchors. It is need to be considering the boundary condition by concrete-anchor connection. In this paper, the seismic analysis was conducted varying anchoring type as non-linear stiffness condition from preliminary analysis.

Nuclear power plants in operation are composed of many electrical equipment, and various types of safety related components are installed in the electrical equipment. These internal components are repeatedly replaced due to aging and their performance improvements during the operation of nuclear power plants. Replacement of safety-related shall demonstrate that no malfunction occurs even under amplified seismic load at the level where the components are mounted on the electrical equipment. Therefore, it is necessary to derive the accurate seismic load from the level where the target components are mounted on electrical equipment through the equipment seismic analysis. To perform seismic analysis of electrical equipment, dynamic characteristics should be extracted through in-situ test and utilize to improve the electrical equipment seismic analysis model. In this study, in-situ test of typical NPP’s electrical equipment is performed to derive a natural frequency and mode shapes in the horizontal direction.

Most of systems and components in nuclear power plants (NPPs) are anchored to the concrete structure and other components by means of post installed anchors. In order to develop more accurate seismic analysis model of equipment in NPPs, a deep consideration of concrete-anchor connection behavior is required. In this paper, the nonlinear finite element analysis was conducted for the concrete-anchor connection zone details. From the analysis results including strength and load-displacement relation was derived according to design variables including geometry and material properties.

In this study, bearing capacities under large lateral displacement were obtained using the formulas suggested by Naeim & Kelly(1999) and ISO 22762 Part.3(2010) and those were compared with the results of Hwang's experiments(2006) to decide which formula is more reasonable

The application of a base isolation to nuclear systems should be considered in lots of view points of operation at the stage of design before construction. Those points includes protection and maintenance of isolators for a seismically isolated nuclear power plant. The methodology suggested in this paper is applicable for any type of isolators in which an isolated structure part is easily replaced and confined pressure can be easily controlled with a height-adjustable part. The height-adjustable part being adjusted by suppling or discharging fluid therein or therefrom