• Nuclear Engineering and Technology
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• 제49권2호
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• pp.306-312
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• 2017

The purpose of this research is to introduce the technical standard of accident sequence precursor (ASP) analysis, and to propose a case study using the dynamic-probabilistic safety assessment (D-PSA) approach. The D-PSA approach can aid in the determination of high-risk/low-frequency accident scenarios from all potential scenarios. It can also be used to investigate the dynamic interaction between the physical state and the actions of the operator in an accident situation for risk quantification. This approach lends significant potential for safety analysis. Furthermore, the D-PSA approach provides a more realistic risk assessment by minimizing assumptions used in the conventional PSA model so-called the static-PSA model, which are relatively static in comparison. We performed risk quantification of a steam generator tube rupture (SGTR) accident using the dynamic event tree (DET) methodology, which is the most widely used methodology in D-PSA. The risk quantification results of D-PSA and S-PSA are compared and evaluated. Suggestions and recommendations for using D-PSA are described in order to provide a technical perspective.

• 한국가스학회지
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• 제7권1호
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• pp.10-18
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• 2003

도시가스시설에서 사고가 발생할 때 그 영향을 평가하는 방법론에 대하여 현실을 고려한 모델을 개발하였다. 즉 사건수목분석(ETA)을 통하여 발생할 수 있는 사고의 형태를 도출하였고 가스의 누출 속도를 음속인 경우와 아음속인 경우에 대하여 계산하였다. 가스의 누출시 화재가 주로 피해를 유발하므로 화재가 발생하여 사망, 화상 및 건물에 피해를 줄 수 있는 경우 그 피해범위를 산정하는 방법을 제시하였다. 마지막으로 적절한 가정을 도입하여 사고로 인한 총 손실비용을 계산하는 방법을 제시하였다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 심포지엄 논문집 정보 및 제어부문
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• pp.81-83
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• 2005

The Reactor Protection System (RPS) is a very important system in a nuclear power plant because the system shuts down the reactor to maintain the reactor core integrity and the reactor coolant system pressure boundary if the plant conditions approach the specified safety limits. This paper describes the unavailability assessment of a digital reactor protection system using the fault tree analysis technique. The fault tree technique can be expressed in terms of combinations of the basic event failures. In this paper, a prediction method of the hardware failure rate is suggested for a digital reactor protection system. and applied to the reactor protection system being developed in Korea.

• International Journal of Control, Automation, and Systems
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• 제4권1호
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• pp.105-112
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• 2006

The main function of a reactor protection system is to maintain the reactor core integrity and the reactor coolant system pressure boundary. Generally, the reactor protection system adopts the 2-out-of-m redundant architecture to assure a reliable operation. This paper describes the safety assessment of a digital reactor protection system using the fault tree analysis technique. The fault tree technique can be expressed in terms of combinations of the basic event failures such as the random hardware failures, common cause failures, operator errors, and the fault tolerance mechanisms implemented in the reactor protection system. In this paper, a prediction method of the hardware failure rate is suggested for a digital reactor protection system, and applied to the reactor protection system being developed in Korea to identify design weak points from a safety point of view.

• Nuclear Engineering and Technology
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• 제55권3호
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• pp.981-988
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• 2023

A seismic event caused an accident at the Fukushima Nuclear Power Plant, which further resulted in simultaneous accidents at several units. Consequently, this incident has aroused great interest in the safety of nuclear power plants worldwide. A reasonable safety evaluation of such an external event should appropriately consider the correlation between SSCs (structures, systems, and components) and the probability of failure. However, a probabilistic safety assessment in current nuclear industries is performed conservatively, assuming that the failure correlation between SSCs is independent or completely dependent. This is an extreme assumption; a reasonable risk can be calculated, or risk-based decision-making can be conducted only when the appropriate failure correlation between SSCs is considered. Thus, this study analyzed the effect of the failure correlation of SSCs on the safety of the system to realize rational safety assessment and decision-making. Consequently, the impact on the system differs according to the size of the failure probability of the SSCs and the AND and OR conditions.

• 한국항해항만학회:학술대회논문집
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• 한국항해항만학회 2019년도 추계학술대회
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• pp.267-267
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• 2019

위험물 운반선에 적재된 물질에 화재나 폭발사고와 같은 선박사고가 발생하는 경우, 그 경로가 매우 복잡하기 때문에 사고의 원인을 추정하기가 어렵다. 이는 사고를 일으킨 원인에 대한 증거가 없거나, 선박 안에서 어떤 화학반응이 일어났는지를 시각적으로 파악하기 힘들기 때문이다. 본 연구에서는 폭발사고를 야기시키는 화학물질에 화학반응식을 도입한 사건가지분석(Event Tree Analysis, ETA)기법을 적용하여 선박에 적재된 화학물의 화재사고 경로를 추정하는 연구를 하였다. 그 결과 다양한 화학반응식을 나타낼 수 있었으며, 그것을 ETA기법에 적용하여 폭발경로를 보다 시각화 할 수 있었다.

• Nuclear Engineering and Technology
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• 제48권2호
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• pp.386-403
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• 2016

The safety of nuclear power plants is analyzed by a probabilistic risk assessment, and the fault tree analysis is the most widely used method for a risk assessment with the event tree analysis. One of the well-known disadvantages of the fault tree is that drawing a fault tree for a complex system is a very cumbersome task. Thus, several graphical modeling methods have been proposed for the convenient and intuitive modeling of complex systems. In this paper, the reliability graph with general gates (RGGG) method, one of the intuitive graphical modeling methods based on Bayesian networks, is improved for the reliability analyses of dynamic systems that have various operation modes with time. A reliability matrix is proposed and it is explained how to utilize the reliability matrix in the RGGG for various cases of operation mode changes. The proposed RGGG with a reliability matrix provides a convenient and intuitive modeling of various operation modes of complex systems, and can also be utilized with dynamic nodes that analyze the failure sequences of subcomponents. The combinatorial use of a reliability matrix with dynamic nodes is illustrated through an application to a shutdown cooling system in a nuclear power plant.

• 한국철도학회논문집
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• 제9권3호
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• pp.264-270
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• 2006

In this paper we present a safety plan to be applied to the development of the TCS(Train Control System). The safety plan that can be applied to the life cycle of a system, from the conceptual design to the dismantlement, shows the whole process of the paper work in detail through the establishment of a goal, analysis and assessment, the verification. In this paper we study about the making a plan, the preliminary hazard analysis, the hazard identification and analysis to guarantee the safety of the TCS. The process far the verification of the system safety is divided into several steps based on the target system and the approaching method. The guarantee of the system safety and the improvement of the system reliability is fellowed by the recommendation of the international standards.

• 전기전자학회논문지
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• 제23권1호
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• pp.254-260
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• 2019

본 논문에서는 양방향 dc-to-dc 컨버터의 고장원인, 고장영향, 고장 결과를 파악하기 위한 failure mode and effect analysis(FMEA)와 양방향 컨버터의 위험도를 고려한 fault-tree analysis(FTA)를 통해 고장률을 예측한다. 전기차의 구동전압을 효율적으로 상승시키기 위해 인버터 앞단에 부착되는 양방향 컨버터는 배터리 전력을 dc-link 커패시터로 방전시키는 승압모드와 회생전력을 배터리로 충전시키는 강압모드를 가진다. 양방향 컨버터의 동작 특성을 고려한 FMEA 결과를 바탕으로 컨버터의 위험도를 고려한 고장나무를 설계한다. 전기차 MCU용에 맞는 설계 파라메타를 설정하고 출력전압 리플과 인덕터 전류 리플에 따른 커패시터와 인덕터의 부품 고장률을 분석한다. 또한 동작 온도에 따른 주요부품의 고장률을 MIL-HDBK-217F를 이용하여 구한다. 마지막으로 부품 고장률을 고장나무의 기본 사상의 고장률로 반영하여 컨버터 고장률과 평균고장시간을 예측한다.

• 한국화재소방학회논문지
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• 제22권5호
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• pp.35-42
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• 2008

최근 KDX-III, LPX 등 대형함 건조사업의 진행으로 예전과 달리 함정 규모가 커지고 함정 내 승조원수 및 승조 인원 구성도 다양화 되고 있는 상황을 반영하여 화재로 인한 해군함정의 위험도를 정량적으로 평가 분석하였다. 이를 위해 해군 함정의 복잡한 화재 전파양상을 사건수목분석(ETA)기법으로 모델링하였고, 승조원 침실 내 화재해석을 위해 CFAST 프로그램을 이용하여 화재 전파양상 및 화재구역 내거주가능시간(임계시간)을 예측하였다. 이를 승조원 탈출 시간과 비교하여 상황별 사망자 수를 산출하였으며 FN-curve로 전반적인 위험도를 도식하여 화재 위험도의 수용여부를 판단할 수 있는 방법을 제시하였다. 본 연구에서 제시된 방법론을 바탕으로 새롭게 건조되는 함정 설계단계에서 화재 발생시 함정에서의 인명위험성을 적절하게 평가할 수 있는 도구로 활용이 가능할 것으로 사료된다.