• International Journal of Safety
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• v.3 no.1
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• pp.32-37
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• 2004

Recently KAERI has developed the severe accident management guidance to establish Korea standard severe accident management system. On the other hand the PC-based severe accident training simulator SATS has been developed, and the MELCOR code is used as the simulation engine. SATS graphically displays and simulates the severe accidents with interactive user commands. The control capability of SATS could make a severe accident training course more interesting and effective. In this paper the development and functions of the electrical hypertext guidance module HyperKAMG and the SATS-HyperKAMG linkage system for the severe accident management are described.

• Journal of the Korean Society of Safety
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• v.12 no.4
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• pp.143-152
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• 1997

Probabilistic Safety Assessment(PSA) is an engineering analysis of the possible contributors to the risk from a nuclear power plant. It consist of three phases named as Level 1, 2 and 3. Level 1 PSA mainly focused in this paper is the phase of system analysis which includes the development of accident scenarios and the frequency estimation of each scenario. It covers also the system reliability analysis, component data analysis, and human reliability analysis. PSA have become a standard tool in safety evaluation of nuclear power plants. The main benefit of PSA is to provide insights into plant design, performance and environmental impacts, including the identification of dominant risk contributors and the comparison of options for reducing risk.

• Korean System Dynamics Review
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• v.2 no.2
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• pp.63-84
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• 2001

There are many activities to improve Nuclear Power Plant(NPP) performance and safety such as equipment improvement, redundancy and the like. Since public perception about NPP safety affects nuclear policy of site selection. Recent researches for NPP safety are including not only technical approaches but also social ones. In. this contexture, the purpose of this study is to develope cuassal loop digaram for assessment of organizational and human factors in NPP safety. Through real data from interview with NPP employees we develope causal loop diagram which can explain the relations of cause and effect among variables, and depict social system for organizational and human factors in NPP safety.

• Journal of the Korean Society of Safety
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• v.20 no.1 s.69
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• pp.7-12
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• 2005

In heavy industrial fields such as power plant and chemical plant, it is often necessary to restore a damaged part of large machinery or structure which is installed in the hazard working place. In this paper, to evaluate the safety of plastic deformed cylindrical beam a finite element technique has been used. The variations of residual stresses on the process of damaging and restoring for surfaces and cross-sections have been examined. The results show that the maximum von Mises stresses occur outer cylinder surfaces of boundary between cylindrical beam support md cylindrical beam when deformation procedure and restoring force is applied. The maximum residual stress remains 158.6MPa in the inner wall and this value correspond to $53\%$ of yield stress then restoration procedure is finished.

• Journal of the Korean Society of Safety
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• v.21 no.1 s.73
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• pp.72-78
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• 2006

In many chemical plants the change or modification is carried out without proper technical review and hazard analysis, and also without adequate technical staff and procedures for comprehensive monitoring of potential hazards resulting from the change. Such changes sometimes affect to the process safety badly if it is not managed properly. Therefore, in order to prevent major industrial accidents caused by change or modification, and also in order to apply Management of Change procedure easily in the field and minimize economic burden of company caused by plant changes, K-MOC(KOSHA-Management of Change) software has been developed and provided to the chemical industry.

• Proceedings of the Korean Nuclear Society Conference
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• 2005.05a
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• pp.1221-1222
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• 2005

Interface control activities during the nuclear power plant (NPP) construction and operation have been reviewed for enhancing the safety of NPP. The primary focus of the study is given on analysis of lessons learned from the recent significant events of Korean Standard Nuclear Power plant (KSNP), such as a series of break-off of thermal sleeves at YGN 5 & 6 and radioactivity leak at YGN 5, in respect of interface control. Based on the results of the analysis, this study recommends measures for the improvement of interface control among utility and technical supporting organizations (TSO), and suggests new regulatory systems, such as reporting of safety significant non-conformances, to effectively verify the adequacy of interface control activities during construction and operation of NPPs.

• Corrosion Science and Technology
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• v.11 no.2
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• pp.43-47
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• 2012

Recently, regulatory bodies quite often encourage to adopt risk-based inspection (RBI) and management programs because they can enhance safety simultaneously with deregulation in Korea. RBI is an integrated methodology that factors risk into inspection and maintenance decision making. This paper describes an example of how to use known risk assessment codes (API 580, API 581 BRD) to address such safety analysis requirements for risk management in the refining industry. Specifically, this paper reports the methodology and the results of implementation to the Crude Distillation Unit(CDU) plant of refinery units using the $KGS-RBI^{TM}$ program, developed by the Korea Gas Safety Corporation in reference of API Codes and ASME PC (Post Construction) with a suitable consideration of Korean situation. The results of the risk and reliability assessment using $KGS-RBI^{TM}$ program are useful in determining whether the detected defects are tolerable or required to be repaired. The subsequent decisions are to manage the future inspection, repair and maintenance planning in the risk reduction control.

• Nuclear Engineering and Technology
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• v.36 no.1
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• pp.64-72
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• 2004

The purpose of this study is to develop a system dynamics model for the assessment of the organizational and human factors in a nuclear power plant which contribute to nuclear safety. Previous studies can be classified into two major approaches. One is the engineering approach using tools such as ergonomics and Probability Safety Assessment (PSA). The other is the socio-psychology approach. Both have contributed to find organizational and human factors and to present guidelines to lessen human error in plants. However, since these approaches assume that the relationship among factors is independent they do not explain the interactions among the factors or variables in Nuclear Power Plants. To overcome these restrictions, a system dynamics model, which can show cause and effect relationships among factors and quantify the organizational and human factors, has been developed. Handling variables such as the degree of leadership, the number of employees, and workload in each department, users can simulate various situations in nuclear power plant organization. Through simulation, users can get insights to improve safety in plants and to find managerial tools in both organizational and human factors.

• Journal of the Korean Institute of Plant Engineering
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• v.23 no.4
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• pp.85-92
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• 2018

With the increasing use of chemicals in domestic businesses, the possibility of fire explosion and poisonous material leakage accidents is also increasing. Accordingly, the Korea Occupational Safety and Health Agency(KOSHA) has implemented the process safety management (PSM) system for a long time. However, process safety report submission has been providing and operating e-PSM since 2016 to address these problems as it is difficult to increase budget spending due to the need for professional capabilities and commissioning the report to consulting institutions. Therefore, this study conducts questionnaires on whether e-PSM system that is well utilized in the field, focusing on existing PSM business sites. In order to find out the activation method that can solve the deficiency factors by analyzing various inconveniences and problems accurately, we propose three improvement methods as educational aspect, promotional direction of e-PSM system, and institutional aspect.

• Proceedings of the Korean Society of Applied Entomolohy Conference
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• 2001.11a
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• pp.60-60
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• 2001