• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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• pp.579-585
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• 1996

A CATHENA model for the reactor regulating system is developed and tested independently. A CATHENA plant model is created by combining this model with the reference CATHENA model which has been developed to analyze a loss-of-coolant accident (LOCA) for the Wolsong 2 generating station. This model is intended to provide a trip coverage analysis capability. The CATHENA reactor regulating system model includes the demand power routine. the light water zone control absorbers, mechanical control absorbers and adjusters. The CATHENA model is tested for steady state at 103% full power. A postulated accident transient (small LOCA) was also tested. The results show that the control routines in CATHENA were set up properly.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 제36회 하계학술대회 논문집 전기설비
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• pp.67-69
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• 2005

Due to the unusual change in the weather to be increased suddenly, the damage of the lightning accident is recently more increased than before. Many water treatment facilities are operated by automatic control or by remote control. Automatic control systems are adopted in water treatment facilities. So there are damaged by lightning inevitably. This study is intended to measure and analyze the lightning accident occurred by the lightning and to show the methods minimizing the lightning accidents.

• Nuclear Engineering and Technology
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• 제36권5호
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• pp.430-449
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• 2004

A quantitative model for a control system that integrates human operators, systems, and their interactions is developed based on discrete functions. After identifying the major entities and the key factors that are important to each entity in the control system, a quantitative analysis to estimate the recovery failure probability from an abnormal state is performed. A numerical analysis based on assumed values of related variables shows that this model produces reasonable results. The concept of 'relative sensitivity' is introduced to identify the major factors affecting the reliability of the control system. The analysis shows that the hardware factor and the design factor of the instrumentation system have the highest relative sensitivities in this model. T도 probability of human operators performing incorrect actions, along with factors related to human operators, are also found to have high relative sensitivities. This model is applied to an analysis of the TMI-2 nuclear power plant accident and systematically explains how the accident took place.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.395-396
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• 2004

• 한국항해항만학회지
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• 제40권6호
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• pp.391-400
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• 2016

최근 우리나라 연근해에서 발생한 몇 건의 대형 해양사고에서, 신속하고 체계적인 초기대응이 사고 전개양상과 사고결과에 얼마나 큰 영향을 미치는지를 확인하였다. 또한, 이를 통해 다양한 해양사고 상황에 대한 정확한 정보와 전개될 수 있는 시나리오, 적용 가능한 사고대응 방법들에 대한 정보를 신속하게 확보하는 것이 해양사고 초기대응을 위하여 무엇보다 중요함을 알 수 있었다. 이러한 현실적인 문제를 해결하기 위한 일환으로, 본 연구에서는, '위험도기반 초기대응 지원 시스템'의 개념을 제시하고, 해양사고 이후 전개 가능한 모든 시나리오와 적용 가능한 사고대응 방법들을 식별하기 위하여 사건전개 시나리오 식별 브레인스토밍 기법을 제안하였으며, 식별된 사고대응 방법들의 적용으로 인한 피해저감 효과 등을 정량화하기 위하여 사건수목분석 (Event Tree Analysis: ETA) 기법을 활용한 사건전개수목을 제안하였다. 그리고 각각의 사고대응 방법에 대한 상세분석을 위해서는 PERT/CPM의 사용을 제안하였다. 또한, 상기 제시한 위험도기반 초기대응 지원시스템의 구성 체계를 설명하기 위하여, 유조선 좌초사고에 대한 사고대응 작업을 예로 간략한 위험도분석 작업을 수행하였다.

• 한국항공우주학회지
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• 제36권5호
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• pp.497-506
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• 2008

이 논문의 목적은 항공기 상태가 정상상태에서 공항에 접근 착륙 중 발생한 사고로서 상업용 항공사에서 발생하는 사고를 예방하기위한 지침이 될 수 있는 사고예방 차원에서 중요한 이정표가 될 수 있다. 이 논문의 CFIT 사고의 주요한 분석은 1993년도부터 2002년까지 발생한 사고 중에서 괌사고, 목포사고 및 김해사고를 중점으로 사고원인분석을 실시하였다.CFIT 사고는 운항승무원에 의해서 사고 전에 충분히 인지하지 못하고 있다가 지상 장애물 또는 해면에 충돌하는 사고로 매우 치명적이다. 일반적으로 CFIT 사고는 대부분의 비행 중에 발생할 수 있지만, 보다 많이 발생하는 경우는 착륙중에 발생함으로 더욱 위험하다고 볼 수 있다.이 논문을 통하여 CFIT 사고를 예방하기위하여 운항승무원 교육 및 훈련을 할 필요가 있다고 사료되며 특별히 EGPWS(향상된 지상충돌경고장비)와 같은 장비를 항공기에 장착하기를 추천하며 항공사의 조직문화에 대한 연구가 더욱 요구된다고 판단한다.

• 해양환경안전학회:학술대회논문집
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• 해양환경안전학회 2004년도 춘계학술발표회
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• pp.29-34
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• 2004

해양사고는 많은 원인이 서로 복잡하게 상호작용을 하여 발생하고 있다. 이러한 해양사고의 분석은 선박의 안전 운항상의측면에서 매우 중요하다고 할 수 있다. 따라서 본 연구의 목적은 시스템다이내믹스법을 이용하여 해양사고 원인과 개선책에 대한 모델을 구축하고, 요소의 개선에 대한 효과를 분석하고자 한다. 본 연구의 수행을 위해 해양사고 원인과 개선책의 요소를 브레인스토밍법에 의해 추출하고, 인과지도상의 정량적, 정성적, 피드백루프로 변환하였다. 그리고 표준모델과 4가지 정책모델에 대해 23년간($1997\~2020$) 시뮬레이션을 수행하였다.

• 한국안전학회지
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• 제28권1호
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• pp.40-46
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• 2013

In the chemical process industries, accidents have a high potential and large effects on catastrophic results. Therefore the safety management for accident prevention plays a crucial role to guarantee the process safety. For these reasons, many systematic methods for safety management system have been widely employed in the fields of chemical processes. PSM (Process safety management) is one of most representative methods. The audit system, which is one of PSM system components, evaluates the performance of PMS system. However, most existing safety audit systems are not systematic and these are performed based on knowledges and experiences of various specialist. Moreover, the safety audit is only performed based on each independent technical component. So, the results of safety audit are not a quantitative index but only a series of commentaries. Finally, it is very difficult to obtain the comparison with other plants or industries. In this study, the novel systematic method and index-based accident database of auditing safety management systems for quantitative assessment are proposed. First, the elements of safety audit replace technical methods to categories of accident database. The F-N curve of each category for accident database is employed to derive the index for quantitative assessment. The Accidental Factor Risk Index (AFRI) is suggested for evaluating the effect of each element in accident database and safety audit system. The safety audit can be modified according to the proposed index.

• 대한안전경영과학회지
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• 제24권1호
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• pp.61-72
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• 2022

This study aims to propose a conceptual design of information displays for supporting responsive actions under severe accidents in Nuclear Power Plants (NPPs). Severe accidents in NPPs can be defined as accident conditions that are more severe than a design basis accident and involving significant core degradation. Since the Fukushima accident in 2011, the management of severe accidents is increasing important in nuclear industry. Dealing with severe accidents involves several cognitively complex activities, such as situation assessment; accordingly, it is significant to provide human operators with appropriate knowledge support in their cognitive activities. Currently, severe accident management guidelines (SAMG) have been developed for this purpose. However, it is also inevitable to develop information displays for supporting the management of severe accidents, with which human operators can monitor, control, and diagnose the states of NPPs under severe accident situations. It has been reported that Ecological Interface Design (EID) framework can be a viable approach for developing information displays used in complex socio-technical systems such as NPPs. Considering the design principles underlying the EID, we can say that EID-based information displays can be useful for dealing with severe accidents effectively. This study developed a conceptual design of information displays to be used in severe accidents, following the stipulated design process and principles of the EID framework. We particularly attempted to develop a conceptual design to make visible the principle knowledge to be used for coping with dynamically changing situations of NPPs under severe accidents.

• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1110-1119
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• 2020

The Floating Absorber for Safety at Transient (FAST) is a safety device used in the innovative Sodium-cooled Fast Reactor (iSFR). The FAST insert negative reactivity under transient or accident conditions. However, behavior of the FAST is still unclear under transient conditions. Therefore, the existing Floating Absorber for Safety at Transient Analysis Code (FASTAC) is improved to analyze the FAST movement by considering the reactivity and temperature distribution within the reactor core. The current FAST system is simulated under a single control rod withdrawal accident condition. In this investigation, the reactor thermal power does not return to its initial thermal power even if the FAST inserts negative reactivity. Only a 9 K of coolant temperature margin, in the hottest fuel assembly at EOL, can lead to unnecessary insertion of the negative reactivity. On the other hand, the FASTs cannot contribute to controlling the reactivity when normalized radial power is less than 0.889 at BOL and 0.972 at EOL. These simulation results suggest that the current FAST design needs to be optimized depending on its installed location. Meanwhile, the FAST system keeps the fuel, cladding and coolant temperatures below their limit temperatures with given conditions.