• 한국시스템다이내믹스연구
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• 제15권2호
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• pp.5-25
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• 2014

The purpose of this study is to analyze the effects of nuclear power plant workers and organizational characteristics on accidents, and seek the combination of policies for reducing accidents. For this purpose, it grasped, by using System Dynamics and Causal Loop Diagram, how various factors that cause accidents in nuclear plants are interrelated, and performed simulations after building simulation models. As a result of the analysis, first, the fundamental cause of safety accidents in nuclear power plants turned out to be the time constraint on the workload. Second, it turned out that as the workload of workers increases, physical and mental stresses increase, thereby increasing accidents due to errors and violations. Third, it turned out that as the levels of educational training and compliance with regulations and procedures are enhanced, accidents are reduced. Lastly, it turned out that as the combination of policies (reliance level + working environment + educational training + compliance with regulations and procedures) is increased, accidents are reduced. Especially, it turned out that if the combination of policies is increased by 30%, more than 10 cases of accidents are reduced.

• Nuclear Engineering and Technology
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• 제55권7호
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• pp.2670-2677
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• 2023

In the nuclear safety studies, a new trend refers to the evaluation of uncertainties as a mandatory component of best-estimate safety analysis which is a modern and technically consistent approach being known as BEPU (Best Estimate Plus Uncertainty). The major objectives of this study consist in performing a study of uncertainties/sensitivities of the major analysis results for a generic CANDU 6 Nuclear Power Plant during Station Blackout (SBO) progression to understand and characterize the sources of uncertainties and their effects on the key figure-of-merits (FOMs) predictions in severe accidents (SA). The FOMs of interest are hydrogen mass generation and event timings such as the first fuel channel failure time, beginning of the core disassembly time, core collapse time and calandria vessel failure time. The outcomes of the study, will allow an improvement of capabilities and expertise to perform uncertainty and sensitivity analysis with severe accident codes for CANDU 6 Nuclear Power Plant.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2022년도 추계학술대회
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• pp.351-353
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• 2022

국내와 국외를 통틀어서 현재까지 원전사고가 수차례 있었고 이로 인한 크고 작은 피해가 있었다. 해외는 이러한 사고를 줄이기 위해서 형상관리라는 기술을 도입하여 원전 운영에 대한 안전성과 신뢰성을 향상 시켜왔다. 본 논문에서는 형상관리에 관한 기본적인 정보와 국외 원전의 형상관리 도입 성공사례들을 통해서 국내에 적용 가능한 기술적 부분을 확인하고 이를 국내 원전에 맞게 보완하여 새로이 적용할 수 있는지를 알아본다.

• 한국시뮬레이션학회논문지
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• 제6권1호
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• pp.85-96
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• 1997

Designing and constructing a proper simulator for real power plants requires extensive research in human engineering and computer science and integration of different fields of technologies such as system analysis, operational knowledge for nuclear plant, etc. A full scope replica type simulator for nuclear power plant is developed. The simulator has the same feature and operational functions as one in the main control room (MCR) of a reference power plant. The simulator provides the necessary training to recover or reduce damages from accidents that usually are unpredictable. This paper describes the configurations and characteristics for the simulator that is developed for Younggwang Nuclear Power Plant #3,4 which is the basic model of the Korean Nuclear Power Plant. The paper also describes technical aspects of Auto Code Generator that is used for developing the simulator. The successful development of the simulator will contribute to improve safety in operation of nuclear power plants.

• 한국재난정보학회 논문집
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• 제19권3호
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• pp.582-596
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• 2023

연구목적: 본 연구는 원전사고 발생 시 임시 대피시설의 안전성을 강화할 수 있는 방안을 연구하였다. 연구방법: 본 연구에서는 과거의 체르노빌, 후쿠시마, 쓰리마일섬(TMI) 원전사고에 대한 사례연구를 활용하였다. 연구결과: 현재의 방사선 비상 대응 계획은 소개에 중점을 두고 있으며, 실내대피 개념은 단순히 주민 대피를 지원하는 수단으로 활용되고 있다. 그러나 사례연구를 통해 INES-5 이상의 사고의 경우, 소개보다 실내대피를 장려하는 것이 사상자 최소화에 효과적임을 확인하였다. 더 나은 실내대피를 보장하기 위해 아파트를 임시 대피소로 활용할 것을 권장하며, 아파트가 방사선 방호 기술을 갖추도록 개선사항을 제안한다. 결론: 더 나은 실내대피를 보장하기 위해 아파트를 임시 대피소로 활용할 것을 권장하며, 차폐, 양압, 밀폐기술을 이용해서 아파트의 성능을 보완하고자 한다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 춘계학술발표회요약집
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• pp.401.2-401
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• 2001

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2003년도 춘계학술발표대회 요약집
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• pp.200.1-200.1
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• 2003

• 산업공학
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• 제13권2호
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• pp.211-216
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• 2000

A methodology that determines the optimal shutdown time of a nuclear power plant is suggested. The shutdown time is decided considering the trade off between the cost of accident and the loss of profit due to the early shutdown. We adopt the bayesian approach in manipulating the model parameter that predicts the accidents. We build decision tree models and apply dynamic programming approach to decide whether to shutdown immediately or operate one more period. The branch parameters in decision trees are updated by bayesian approach. We apply real data to this model and provide the cost of accidents that guarantees the immediate shutdown.

• 산업공학
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• 제6권2호
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• pp.79-89
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• 1993

We develop a statistical model to describe nuclear power plant accidents and predict time to next accident of various levels. We adopt Bayesian approach to obtain posterior and predictive distributions for the time to next accident. We also derive an approximation method to solve many dimensional numerical integration problems that we often encounter in a Bayesian approach. We introduce Influence Diagrams in modeling, and parameter updating, thereby the dependency or independency among model parameters are clearly shown. Also Separable Updating Theorem is utilized to easily obtain the posterior distributions.

• Journal of applied mathematics & informatics
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• 제8권2호
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• pp.505-518
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• 2001

The huge and complicated plants such as nuclear power stations are likely to cause the operators to make mistakes due to a variety of inexplicable reasons and symptoms in case of emergency. That’s why the prevention system assisting the operators is being developed for. First of all. I suggest an improved fuzzy diagnosis. Secondly, I want to demonstrate that a classification system of nuclear plant’s accident investigating the causes of accidents foresees possible problems, and maintains the reliability of the diagnostic reports in spite of improper working in part. In the event of emergency in a nuclear plant, a lot of operational steps enable the operators to find out what caused the problems based on an emergent operating plan. Our system is able to classify their types within twenty to thirty seconds. As so, we expect the system to put down the accidents right after the rapid detection of the damage control-method concerned.