• Journal of the Korean GEO-environmental Society
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• v.20 no.7
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• pp.5-10
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• 2019

In recent Gyeongju and Pohang earthquakes, motions that exceed the design ground motion were recorded. This has led to adjustments to the design earthquake intensity in selected design guidelines. An increment in the design intensity requires reevaluation of all associated facilities, requiring extensive time and cost. Firstly, the seismic factor of safety of built concrete retaining walls are calculated. Secondly, the seismic margin of concrete retaining walls is evaluated. The design sections of concrete walls built at power plants and available site investigation reports are utilized. Widely used pseudo-static analysis method is used to evaluate the seismic performance. It is shown that all concrete walls are safe against the adjusted design ground motion. To determine the seismic margin of concrete walls, the critical accelerations, which is defined as the acceleration that causes the seismic factor of safety to exceed the allowable value, are calculated. The critical acceleration is calculated as 0.36g~0.8g. The limit accelerations are significantly higher than the design intensity and are demonstrated to have sufficient seismic margin. Therefore, it is concluded that the concrete retaining walls do not need to be reevaluated even if the design demand is increased up to 0.3g.

• Journal of the Earthquake Engineering Society of Korea
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• v.3 no.1
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• pp.75-92
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• 1999

In this paper, the seismic analysis model for seismically isolated KALIMER reactor structures is developed and the modal analysis and the seismic time history analysis are carried out for seismic isolation and non-isolation cases. To check the seismic stress limit according to the ASME Code, the equivalent seismic stress analyses are preformed using the 3-D finite element model. From the seismic stress analysis, the seismic margins are calculated for structural members. The limit of seismic load is defined to show that the maximum input acceleration ensures the structural safety for seismic load. In comparison of seismic responses between seismic isolation and non-isolation cases, the seismic isolation design gives significantly reduced acceleration responses and relative displacements between structures. The seismic margin of KALIMER reactor structure is high enough to produce the limit seismic load 0.8g.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11b
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• pp.683-689
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• 1996

본 논문의 목적은 현재 국내에서 개념설계중인 KALIMER(Korea Advanced LIquid MEtal Reactor) 원자로구조물에 대한 면진성능과 내진여유도를 평가하여 이들 성능을 향상시킬 수 있는 주요 설계변경 부위를 검토하는 것이다. 이를 위하여 ANSYS 범용 유한요소해석코드를 이용하여 원자로구조물에 대한 3차원 유한요소해석모델을 작성하고 이로부터 집중질량 스프링으로 이루어진 지진해석모델을 개발하여 지진해석을 수행하였다. KALIMER 원자로 구조물에 대한 내진평가결과 내진능력(Seismic Capability)은 0.35g로 나타났으며 이는 Reactor Vessel Liner, Separation Plate그리고 Support Barrel의 연결부위의 수직 강성을 증가시키는 설계변경을 통하여 크게 향상될 수 있는 것으로 나타났다.

• Proceedings of the Earthquake Engineering Society of Korea Conference
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• 2002.03a
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• pp.239-249
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• 2002

The Turbine Building of nuclear power plant is classified as non safety-related structure. During the operation, there may be possibility the original licensing basis would be changed, which makes non safety-related structure safety-related. Such a change in regulation requires utility to perform seismic qualification for the existing structure and their facilities. Thus it is meaningful to evaluate seismic margin of the existing non-qualified building structure. In addition, in this paper it is shown that a modification to the structure can enhance their seismic capacity.

• Proceedings of the Earthquake Engineering Society of Korea Conference
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• 2002.03a
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• pp.220-227
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• 2002

This study introduces the fragility analysis method for the safety evaluation of reinforced concrete pier subject to earthquake. Damage probability is calculated instead of the failure probability from definition of the damage state in the fragility curve. Not only the damage model determined by the response of structure subject to earthquake, but also the plastic-damage model which can represent the local damage is applied to fragility analysis. The evaluation method of damage state by damage variable in global structure is defined by this procedure. This study introduces the fragility analysis method considering the features of nonlinear time history behavior of reinforced concrete element and the plastic behavior of materials. At last, This study gives one of the approach method for seismic margin evaluation with the result of fragility analysis to design seismic load.

• Journal of the Earthquake Engineering Society of Korea
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• v.3 no.2
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• pp.97-106
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• 1999

In order to check the necessity of seismic reinforcement for a great number of existing structures effectively, it might be desirable to introduce the multi-step seismic evaluation system. This paper presents close relationships between shear-to-moment capacity ratio of a member and seismic performance of structures concerned through the failure mechanism investigation in the view of geological and structural characteristics. Based on it, the simple seismic performance evaluation method has been proposed and its effectiveness was verified by comparing with the damage condition of structures damaged under Hyogo-Ken Nambu Earthquake.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.14 no.2
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• pp.11-15
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• 2018

A development plan for seismic capacity verification procedures of nuclear components based on the elastic-plastic strain (EPS) features is explained in this paper. The EPS methodology is more realistic to assess seismic responses of components to extreme seismic events beyond the safe shutdown earthquake (SSE) than current practices with the criteria of stress limits. The EPS based approach to analyze the seismic capacity of components can reduce over-conservatism in the current stress-based criteria and can incorporate the seismic responses of components deformed in plastic behavior by the motion of extreme earthquake.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.25 no.1
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• pp.57-64
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• 2012

Since a seismic exceeding design load can result in exposing radioactive material during disposal process of radioactive wastes, the repository should be designed with enough seismic margin. In this paper, a seismic fragility analysis was performed to evaluate the seismic capacity of surface facility structures. According to the analysis results, since inspection & store facility and radioactive waste facility have a rectangle geometry, the seismic capacity was differently presented about 23%~43% according to the axis of structures. The HCLPF capacity of inspection & store facility and radioactive waste facility was 0.52g and 0.93g, respectively. And it was observed that seismic capacity of radioactive waste facility was similar to that of a containment for nuclear power plants.

• Proceedings of the Earthquake Engineering Society of Korea Conference
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• 2000.04a
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• pp.97-104
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• 2000

Evaluating a Review-Level Ground Motion is a key to efficiently perform Seismic Margin Assessment of nuclear power plants whose purpose is to determine a ground motion level for which a plant has high-confidence-of-a-low-probability of seismic-induced core damage and to identify any weaker-link components. In this study a method to obtain RLGMs is reviewed which is recommended by Electric Power Research Institute and implemented to be applied to Limerick site in eastern and central U. S as a case study. This method provides reasonable and site-specific RLGMs as minimum required plant HCLPF for SMA that meet a target mean seismic core-damage frequency based on seismic hazard results and generic values of uncertainty and randomness parameters of the core-damage fragility curves. In addition high-frequency RLGM is justifiably modified to reflect the increased seismic capacity of high-frequency components and spatial variation and incoherence of input ground motion on a basemat of large structures by establishing a method to obtain high0-frequency reduction factors according to EPRI guidelines.

• Proceedings of the Korean Institute of Industrial Safety Conference
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• 2001.11a
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• pp.169-174
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• 2001

원자력발전소 배관계통에 존재하는 균열을 해석하는 방법으로, 이제까지는 균열을 고려하지 않은 상태에서 지진하중을 고려한 탄성 배관해석을 수행하여, 배관에 작용하는 하중을 구한 후, 다음 단계에서 파괴해석 방법으로 균열을 가정한 탄소성 균열해석을 수행하는 2단계의 해석을 통해 균열안정성을 평가해 왔다. 이러한 방법은 전체 배관의 거동과 배관 내에 존재하는 균열의 거동을 서로 독립적인 것으로 고려하고 있으며 재료물성치로는 설계값을 사용하는 등의 보수적인 가정들을 포함하고 있어 배관에 작용하는 하중 또는 응력을 과도하게 계산하는 결과를 초래하고 있다 특히, 지진하중과 같은 반복적인 외부 동적하중이 작용하는 경우, 배관에 국부적인 소성변형이 발생함에도 이를 단지 탄성거동으로 간주하게 되는 것이다. 이러한 몇몇 보수적 가정들을 포함하고 있는 기존의 해석방법은 지나친 보수성을 가질 뿐만 아니라, 균열에 의한 실제 배관의 파단하중과 계산에 의한 파단하중의 비교로서 배관의 안전여유도를 예측하는 방법으로는 적절하지 못하다.(중략)