• Journal of the Earthquake Engineering Society of Korea
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• v.13 no.4
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• pp.15-23
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• 2009

An experimental study was performed to evaluate seismic reduction performance and the applicability of 2-dimensional floor isolation system to the main control room of a nuclear power plant. A lead-rubber bearing (LRB) and a friction pendulum system (FPS) were designed and fabricated for a 2-dimensional floor isolation system. A partial experimental model of a main control room with the LRB and FPS was tested using a shaking table. The experimental model consisted of a control panel, a 2.5m${\times}$2.5m access floor, and four LRB and FPS. The artificial time histories based on the horizontal floor response spectrums (OBE, SSE) of the main control room were used as earthquake input signals. Compared to the non-isolated system, the seismic response of experimental models using a 2-dimensional floor isolation system showed considerable seismic reduction performance against an earthquake.

• Journal of the Korean Institute of Gas
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• v.27 no.4
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• pp.27-33
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• 2023

In a petrochemical plant, various mechanical equipments and structures are interconnected to ensure operability. Since the production activities of petrochemical plants have a great impact on the national economy, it is very important to maintain not only structural safety but also the operability of the facilities. However, the current seismic design standards present the design requirements of facilities mainly aimed at preventing collapse, and do not provide the requirements for securing operability of facilities. Depending on the behavioral characteristics of the facility, operability of the facility can be secured by seismic performance levels other than the collapse prevention level, so it is necessary to present seismic design methods that can apply various seismic performance levels. Spherical (ball) storage tanks are supported by columns and braces and exhibit complex nonlinear behavior because of buckling and yielding of support members. In this study, nonlinear seismic behavior characteristics were statistically analyzed and a new performance-based seismic design method was proposed based on them.

• Journal of the Korean Society for Precision Engineering
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• v.22 no.12 s.177
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• pp.131-140
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• 2005

Responses of the cabinet of the reactor safety system under seismic leadings are analyzed, its dynamic characteristics and structural reliability being evaluated. Analyzed natural frequencies are compared with those measured from a resonance test. Structural safety of the cabinet is evaluated in consideration of the required response spectrums of the operation-base and safe-shutdown earthquakes. Transient responses of the cabinet are analyzed with input ground acceleration measured during the seismic test, accelerations being extracted at the locations of the main internal parts. The transient responses are compared with those from the seismic test, favorable results being shown.

• Proceedings of the KSME Conference
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• 2001.11a
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• pp.465-470
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• 2001

In this study, the seismic analysis of rack structure with fluid-structure interaction is performed through use of the Finite Element Method(FEM) code ANSYS. Fluid-structure interaction can specify in terms of an hydrodynamic effect which is defined as the added mass per unit length divided by the area of the cross section. Using the Floor Response Spectrum(FRS) obtained through the time-history analysis, modal analysis and seismic analysis under Operating Basis Earthquake(OBE) and Safe Shutdown Earthquake(SSE) condition is carried out. The fluid-structure interaction effects on the rack structure are investigated.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2011.10a
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• pp.480-485
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• 2011

In this study, the seismic analysis of power plant piping system was performed using finite element model. This study was performed by ANSYS 12.1. For qualification of power plant piping system, the response spectrum analysis was performed using the given operating basis earthquake(OBE) and safe shutdown earthquake(SSE) floor response spectrum. The maximum stresses of power plant piping system were 166 MPa under OBE condition and 281 MPa under SSE condition. Thus, it can shown that the structural integrity of tpower plant piping system has a stable structure for seismic load conditions.

• KSCE Journal of Civil and Environmental Engineering Research
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• v.35 no.2
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• pp.255-264
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• 2015

Steel plate concrete (SC) structure has been developed as a new structural type. Rational damping value shall be determined for the seismic design of SC structure. This study evaluated damping ratio of SC structure through experiments. For the study, a SC shear wall specimen was constructed and dynamically tested on the shaking table. Acceleration time history responses measured from testing were converted to the transfer functions and analyzed by using experimental modal analysis technique. The structural damping ratio of the specimen was identified as 4% to critical. Considering the shaking table test was performed at the excitation level corresponding to the low stress level of the specimen, 4% could be suggested as a structural damping for design of SC structure for operating basis earthquake.

• Proceedings of the KIEE Conference
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• 2001.04a
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• pp.63-66
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• 2001

원자력발전소는 지진과 같은 자연재해나 극한 운전조건에서 방사능물질이 외부로 누출되는 것을 방지하도록 설계 되어야한다. 따라서 이와 관련된 안전등급기기는 원전설비의 정상운전조건뿐 아니라 원전설계기준 사고조건(DBE, Design Basis Events)에서도 그 안전성 관련 기능이 검증되어야 한다. 본 연구에서는 국내 원자력 발전소의 다양한 환경조건을 만족하며 엄격한 기기검증요건에 따라 당사가 수행한 안전등급(Class 1E) 저압 유도전동기의 개발사례를 중심으로 방사능노출시험, 가속열노화해석 및 시험, 내진해석 및 시험으로 구성되는 기기검증의 절차와 방법을 제시하였다.

• Journal of the Earthquake Engineering Society of Korea
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• v.16 no.1
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• pp.37-45
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• 2012

In an effort to further exploit the peak ground-motion acceleration (PGA) information per second available in real time by the enacted law, bracketed summations of the PGA per second ($BSPGA_k$) for 30 seconds based on the records with a rate of 100 samples were compared with the cumulative absolute velocity (CAV) and earthquake intensities based on a worldwide database of records from small-to-large earthquakes. The CAV, currently in use as an earthquake damage indicator for nuclear power plants due to its strong correlation with the earthquake intensity, has the disadvantage of requiring a massive amount of digital data with a rate of more than 100 samples per second. The comparative study shows that the $BSPGA_k$ is well correlated with the CAV over the wide range of strong ground-motion levels, which suggests that the $BSPGA_k$ is one of the new promising ground-motion parameters especially useful for rapid earthquake alert notifications through an earthquake monitoring network. Based on the domestic database of records from small-to-moderate earthquakes with felt reports, it is also observed that the $BSPGA_k$ is comparable to the CAV and better than the PGA in predicting the intensity by using the correlation relation.

• Journal of the Korean Society for Nondestructive Testing
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• v.13 no.4
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• pp.42-46
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• 1994

원자력발전소(原子力發電所)의 방진기의 역할은 운전중(運轉中) 지진(地震)이나 혹은 수격작용(水擊作用)등 순간적인 동적 하중의 발생으로부터 관련 배관(配管)과 기기(機器)를 보호하는 것이다. 1989년 이후 ASME Sec. XI에서 50kips 이상의 대형 방진기도 ASME/ANSI OM Part 4에 따라 육안검사(肉眼檢査) 및 성능시험(性能試驗)을 할 것을 추가 요구하고 있다. 따라서 본 보고서는 방진기(防震機) 기능, 미국 원전 방진기의 손상 사례, 검사(檢査) 기술기준(技術基準) 및 요구사항(要求事項)을 검토(檢討)하여 검사 및 성능시험을 적절한 제반 기술기준에 의거 수행토록 하며, 수행 결과 수반되는 손상 방진기에 대한 원인규명(原因糾明)과 까다로운 후속조치(後續措置)의 실시로 원전 40여년 수명기간동안 배관계통(配管系統) 및 기기(機器)의 건전성을 확보하는데 기여코자 한다.

• Proceedings of the KIEE Conference
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• 2005.10c
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• pp.13-16
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• 2005

원자력발전소의 안전과 관련된 기기는 원전의 정상상태 운전조건뿐만 아니라 원전의 설계기준사고 조건에서도 기기의 안전관련 기능을 충분하게 수행할 수 있음이 입증되어야만 한다. 아울러 기기의 설치 환경은 원전의 설계기준사고조건(DBE))으로서 지진만이 고려되는 온화한 환경(mild zone)과 냉각재상실사고(LOCA) 주증기관파단사고(MSLB) 등과 같이 고온, 고압 등의 환경요건이 급격히 변화하는 가혹한 환경(harsh zone)으로 구별되므로 안전관련 기기의 검증 또한 이러한 환경요건에 따라 수행되어져야 한다. 본 연구에서는 당사가 개발한 가혹환경용 안전관련 고압전동기의 개발사례를 중심으로 가혹환경요건에 대한 기기의 검증절차와 방법을 제시하였다.