• Journal of Korean Society of Coastal and Ocean Engineers
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• v.22 no.1
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• pp.18-24
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• 2010

In this study, a tsunami fragility methodology was determined for a probabilistic safety assessment(PSA) induced tsunami event in Nuclear Power Plant(NPP) site. For this purpose, a fragility evaluation method was presented using previous external PSA method. Failure mode and failure criteria about major safety related equipments and structures were determined. Finally, a tsunami fragility assessment was performed for offsite transformer in NPP site. For the fragility evaluation, structural failure like overturning and sliding and functional failure induced by inundation. Through this study, it can be concluded that a functional failure according to inundation height was governed total probability of failure of offsite transformer in NPP.

• Magazine of the Korean Society of Hazard Mitigation
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• v.4 no.3 s.14
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• pp.23-27
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• 2004

• Journal of the Korea Society of Computer and Information
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• v.10 no.6 s.38
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• pp.337-344
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• 2005

In order to Perform a PSA. it requires a large number of data for various fields. Therefore, the effective management of the data is essential to perform and review a PSA and to maintain the quality of a PSA. Korea Atomic Energy Research Institute (KAERI) is developing a PSA information management system (AIMS: Advanced Information Management System for PSA) which enhances the accessibility to PSA information for all PSA related activities. The AIMS is a database system that stores all references and links to the information used for the PSA analysis. The AIMS consists of a database, information browsing modules and a PSA model manager. This Paper describes how we implemented such a database centered application in the view of two areas, database design and data (document) service.

• Proceedings of the Korean Information Science Society Conference
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• 2005.11b
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• pp.133-135
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• 2005

원자력발전소의 정량적 위험성 평가를 위해서 확률론적 안정성 평가 기법이 이용되고 있다. 확률론적 안전성 평가를 수행하기 위해서는 여러 가지 분야의 다양한 신뢰도 데이터가 필요한데, 이를 위한 각종의 신뢰도 자료 중에 인간의 지각 행위 및 수행 행위로부터 발생하는 인적 오류 확률은 그 특성상 실질적이 오류 확률을 얻기가 매우 어렵다. 그래서 인적 오류 확률을 구하기 위해서는 인간 신뢰도 분석분야의 전문가들이 제안한 인간 신뢰도 분석 방법을 이용하여 인적 오류 확률을 추정한다. 한국 원자력 연구소에서는 이를 위해 인간의 지각 및 수행 행위에서 야기되는 인간 오류 사건을 관리하고 인적 오류 확률을 추정하기 위한 인간 신뢰도 분석 시스템을 개발하고 있다. 본 연구에서는 인간 신뢰도 분석 시스템의 개발 과정 및 데이터베이스 설계 그리고 입출력 시스템의 설계에 관하여 기술하였다.

• Journal of the Earthquake Engineering Society of Korea
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• v.12 no.2
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• pp.33-44
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• 2008

Most of the civil structure - bridges, offshore structures, plant, etc. - have been designed by the classical approaches which deal with all the design parameters as deterministic variables. However, some more advanced techniques are required to evaluate the inherent randomness and uncertainty of each design variable. In this research, a seismic safety assessment algorithm based on the structural reliability analysis has been formulated and computerized for more reasonable seismic design of turbine-generator foundations. The formulation takes the design parameters of the system and loading properties as random variables. Using the proposed method, various kinds of parametric studies have been performed and probabilistic characteristics of the resulted structural responses have been evaluated. Afterwards, the probabilistic safety of the system has been quantitatively evaluated and finally presented as the reliability indexes and failure probabilities. The proposed procedure is expected to be used as a fundamental tool to improve the existing design techniques of turbine-generator foundations.

• Proceedings of the Korean Institute of Industrial Safety Conference
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• 2003.05a
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• pp.114-119
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• 2003

원자력발전소를 비롯한 위험 시설물의 확률론적 안전성 평가(Probabilistic Safety Assessment: PSA)는 고장수목(Fault Tree) 및 사건수목(Event Tree) 분석으로 이루어지며, 분석 결과로 그 시설물의 위험도(Risk)는 최소단절집합(Minimal Cutsets)들의 합으로 구성 된다.(중략)

• Tunnel and Underground Space
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• v.14 no.3
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• pp.203-214
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• 2004

For total system performance of a potential radwaste repository, a hypothetical site is assumed with feasible boundary conditions. Assuming a coastal repository, the sensitivity of the depth and the location of a repository along with the distance to a joint on groundwater transport pathways is studied. Results from Connectflow analysis could be used as input of the MASCOT-t the probabilistic safety assessment code.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.3
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• pp.171-188
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• 2012

A GoldSim template program for a safety assessment of a hybrid-typed repository system, called "A-KRS," in which two kinds of pyro-processed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyro-processing of PWR nuclear spent fuels are disposed of, has been developed. This program is ready both for a deterministic and probabilistic total system performance assessment which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios. The A-KRS has been deterministically assessed with 5 various normal and abnormal scenarios associated with nuclide release and transport in and around the repository. Dose exposure rates to the farming exposure group have been evaluated in accordance with all the scenarios and then compared among other.

• Journal of the Earthquake Engineering Society of Korea
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• v.14 no.4
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• pp.17-22
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• 2010

In this study, a tsunami hazard curve was determined for a probabilistic safety assessment (PSA) of a tsunami event at a Nuclear Power Plant site. A Tsunami catalogue was developed by using the historical tsunami record prior to 1900 and the instrumental tsunami record after 1900. For the evaluation of the return period of the tsunami run-up height, power-law, upper-truncated power law and exponential function were considered for the assessment of regression curves and each result was compared. Although there were in total only 9 tsunami records on the east coast of Korea during the time period of the tsunami catalogue, there is no research like this about tsunami hazard curve evaluation, so this research lays a foundation for probabilistic tsunami hazard assessment (PTHA)

• Journal of the Earthquake Engineering Society of Korea
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• v.8 no.6 s.40
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• pp.23-29
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• 2004

The design earthquake used for the seismic analysis and design of NPP (Nuclear Power Plant) is determined by the deterministic or probabilistic methods. The probabilistic seismic hazard analysis(PSHA) for the nuclear power plant sites was performed for the probabilistic seismic risk assessment. The probabilistic seismic hazard analysis for the nuclear power plant site had been completed as a part of the probabilistic seismic risk assessment. The probabilistic method become a resonable method to determine the design earthquakes for NPPs. In this study, the defining method of the probability based scenario earthquake was established, and as a sample calculation, the probability based scenario earthquakes were estimated by the de-aggregation of the probabilistic seismic hazard. By using this method, it is possible to define the probability based scenario earthquakes for the seismic design and seismic safety evaluation of structures. It is necessary to develop the rational seismic source map and the attenuation equations for the development of reasonable scenario earthquakes.