• 건설안전기술
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• 통권49호
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• pp.92-102
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• 2009

Earthquake is one of the hazard so hard because it is difficult predicted occurred time, scale and characters. Due to a recent Sichuan earthquake in China with a magnitude of 7.8, it is worried about having a major earthquake in Korea peninsula in near future. The earthquake in Kobe, Japan showed that the damages were concentrated on the buildings which were not considered to be protected from the earthquakes. In this study, apartment structures in Korea analyze about earthquake hazard and evaluate seismic performance. Through the this study we have notice of earthquake hazard for apartment structures which live a lot of population of Korea and suppose necessary for seismic retrofit.

• 한국지진공학회:학술대회논문집
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• 한국지진공학회 1997년도 춘계 학술발표회 논문집 Proceedings of EESK Conference-Fall 1997
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• pp.217-224
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• 1997

The safety related equipments for use in nuclear power plants should be subjected to the seismic qualification in order to insure the safety of the nuclear power plant. This paper summarizes the seismic qualification test on the Low Voltage Motor Control Centers(MCC's) for use in Wolsong Nuclear Power Plants, Units 2, 3 and 4. The seismic qualification test was performed on the two prototype MCC's(a two-bay wide unit for Phase #1 Test and a five-bay wide unit for Phase #2 Test). The specimens were electrically powered and monitored during the test process. It was demonstrated that the specimens possessed sufficient structural and electrical integrity to withstand the required seismic conditions.

• 한국안전학회지
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• 제23권6호
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• pp.100-107
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• 2008

Earthquake is one of the hazard so hard because it is difficult predicted occurred time, scale and characters. Due to a recent Sichuan earthquake in China with a magnitude of 7.8, it is worried about having a major earthquake in Korea peninsula in near future. The earthquake in Kobe, Japan showed that the damages were concentrated on the buildings which were not considered to be protected from the earthquakes. In this study, apartment structures in Korea analyze about earthquake hazard and evaluate seismic performance. Through the this study we have notice of earthquake hazard for apartment structures which live a lot of population of Korea and suppose necessary for seismic retrofit.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.591-592
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• 2005

• 한국안전학회지
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• 제13권4호
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• pp.286-291
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• 1998

이 논문은 기기검증 중 내진검증(안전)을 위한 접근방법의 일환으로 실험을 통한 유한요소 해석 모델을 개발하였다. 이 모델은 한국원자력연구소 내의 하나로원자로 전기설비 중의 일부분인 UPS를 내진검증하기 위한 것이다. 이 시험증명용 모델은 50Hz 미만의 모든 주요 모드에서 고유진동수가 약 5%이내의 오차를 갖는 값을 예측하였다. 이 모델은 내진검증을 위한 최종 응력해석에 적합하였으며 실제 기기의 동적특성의 예측에 고 정밀도를 보여주었다.

• Nuclear Engineering and Technology
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• 제29권5호
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• pp.417-431
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• 1997

To resolve a general argument about OBE elimination for the future nuclear power plant design, seismic responses of reactor vessel internals and fuel assembly for Ulchin nuclear power plant units 3 and 4 in Korea are investigated as an example. Dynamic analyses of the coupled internals and core are performed for the seismic excitations using the reactor vessel motions. By investigating the response relations between OBE and SSE and their response characteristics, the critical components for OBE loading are addressed. Also the fuel assembly responses are calculated using the core plate motions and their behavior is found to be insignificant for OBE elimination.

• International Journal of Safety
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• 제10권1호
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• pp.22-31
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• 2011

Seismic response control method of the bridge structures with semi-active control device, i.e., magneto-rheological (MR) damper, is studied in this paper. Design of various kinds of clipped optimal controller and fuzzy controller are suggested as a semi-active control algorithm. For determining the control force of MR damper, clipped optimal control method adopts bi-state approach, but the fuzzy control method continuously quantifies input currents through fuzzy inference mechanism to finely modulate the damper force. To investigate the performances of the suggested control techniques, numerical simulations of a multi-span continuous bridge system subjected to various earthquakes are performed, and their performances are compared with each other. From the comparison of results, it is shown that the fuzzy control system can provide well-balanced control force between girder and pier in the view point of structural safety and stability and be quite effective in reducing both girder and pier displacements over the existing control method.

• Computers and Concrete
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• 제13권5호
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• pp.633-648
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• 2014

The seismic safety of concrete dams is one of the important problems in the engineering due to the vast socio-economic disasters which may be caused by collapse of these infrastructures. The accuracy of the risk evaluation associated with these existing dams as well as the efficient design of future dams is highly dependent on a proper understanding of their behaviour due to earthquakes. This paper develops an anisotropic damage model for arch dam under strong earthquakes. The modified Drucker-Prager criterion is adopted as the failure criteria of the dynamic damage evolution of concrete. Some process fields and other necessary information for the safety evaluation are obtained. The numerical results show that the seismic behaviour of concrete dams can be satisfactorily predicted.

• Nuclear Engineering and Technology
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• 제55권2호
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• pp.792-799
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• 2023

Non-reactor nuclear facilities are increasing remarkably in Korea combined with advanced technologies such as life and space engineering, and the diversification of the nuclear industry. However, the absence of a basic classification guideline related to the design of non-reactor nuclear facilities has created confusion whenever related projects are carried out. In this paper, related domestic and international technical guidelines are reviewed to present the classification criteria of non-reactor nuclear facilities in Korea. Based on these criteria, the classification of structures, systems and components (SSCs) for safety controls is presented. Using the presented classification criteria, classification of a hot cell facility, a representative non-reactor nuclear facility, was performed. As a result of the classification, the hot cell facility is classified as the hazard category 3, accordingly, the safety class was classified as non-nuclear safety, the seismic category as non-seismic (RW-IIb), and the quality class as manufacturers' standards (S).

• 대한안전경영과학회지
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• 제25권2호
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• pp.187-192
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• 2023

In piping systems, trapeze hangers are subjected to vertical and horizontal seismic loads and stiffeners are used. In this study, monotonic compression tests were conducted with the removable stiffeners using three variables: stiffener clamp fixing position, section length, and installation direction. The maximum load reinforced with stiffeners could withstand a compressive load of 11kN by applying a safety factor of 10%. It could be estimated that the fixing clamp spacing or the length of shape and load had a proportional relationship. And the stiffener must be fixed in the direction of the strong axis on hinge parts. Also the stiffener buckiling load design proposes to use a method of calculate the flexural buckling compressive strength of and unreinforced full threaded bolt.