• 한국통신학회논문지
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• 제18권4호
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• pp.537-548
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• 1993

OSI 장애 관리 기능 서비스는 경보 보고 기능, 사건 보고 관리 기능 그리고 로그 제어 기능의 서비스로 구성된다. 장애 관리는 사건을 통지하고 관리하는 것이며, 장애 관리 정보로 전달되는 경보 데이터는 효과적으로 관리되어져야 한다. 그리고 이러한 기능들을 사용하여 적절한 장애 관리 모델을 설정하는 것은 네트워크 관리 활동의 연구에 필수적이다. 따라서, 본 논문에서는 경보 보고 기능 서비스를 기반으로 사건보고 관리와 로그 제어 기능의 통합 모델을 연구한다. 또한, 효과적인 OSI 장애 관리를 위하여 관리자 시스템내에 부가된 경보 수집자 요소를 제안하고 연구한다.

• 자원환경지질
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• 제49권2호
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• pp.97-104
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• 2016

본 연구에서는 한반도 남동부지역 주요단층인 양산단층대 주단층이 지나는 울산시 상천리일대 3개 단층점토 지점의 각 3개 입도분리 시료에 대한, 일라이트 폴리타입 정량분석법, K-Ar 연대측정, 일라이트 혼합연대해석법(IAA)법 적용 및 해석을 통해 단층 재활동 절대연대를 결정하였다. 연대측정 및 해석결과, 상천리지점 단층시료에서 41.5~43.5 및 50.7 Ma의 2회 천부단층 재활동연대를 결정하였다. 본 연구결과는 양산단층에 대한 최초의 단층 재활동연대를 직접적인 방법으로 결정한 것으로, 양산단층 생성시기가 이 시기 이전이었으며, 최소 2회 이상의 재활동이 있었음을 의미한다. 양산단층대의 단층점토에 대한 추가적인 연대측정이 이루어질 경우 양산단층의 재활동 시간대를 구체화할 수 있을 것으로 생각된다.

• 한국안전학회지
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• 제31권5호
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• pp.187-194
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• 2016

A single fire event within a fire area can cause multiple initiating events considered in internal events probabilistic safety assessment (PSA). For an example, a fire event in turbine building fire area can cause a loss of the main feed-water and loss of off-site power initiating events. This fire initiating event could result in special plant responses beyond the scope of the internal events PSA model. One approach to address a fire initiating event is to develop a specific fire event tree. However, the development of a specific fire event tree is difficult since the number of fire event trees may be several hundreds or more. Thus, internal fire events PSA model has been generally constructed by modifications of the pre-developed internal events PSA model. New accident sequence logics not covered in the internal events PSA model are separately developed to incorporate them into the fire PSA model. Recently, many fire PSA models have fire induced initiating event fault trees not shown in an internal event PSA model. Up to now, there has been no analytical comparative study on the constructions of fire events PSA model using internal events PSA model with and without fault trees of initiating events. In this study, the changing process of internal events PSA model to fire events PSA model is analytically presented and discussed.

• Nuclear Engineering and Technology
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• 제37권3호
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• pp.259-264
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• 2005

This paper presents a vital area identification (VAI) method based on the current fault tree analysis (FTA) and probabilistic safety assessment (PSA) techniques for the physical protection of nuclear power plants. A structured framework of a top event prevention set analysis (TEPA) application to the VAI of nuclear power plants is also delineated. One of the important processes for physical protection in a nuclear power plant is VAI that is a process for identifying areas containing nuclear materials, structures, systems or components (SSCs) to be protected from sabotage, which could directly or indirectly lead to core damage and unacceptable radiological consequences. A software VIP (Vital area Identification Package based on the PSA method) is being developed by KAERI for the VAI of nuclear power plants. Furthermore, the KAERI fault tree solver FTREX (Fault Tree Reliability Evaluation eXpert) is specialized for the VIP to generate the candidates of the vital areas. FTREX can generate numerous MCSs for a huge fault tree with the lowest truncation limit and all possible prevention sets.

• Ocean Systems Engineering
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• 제9권3호
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• pp.261-285
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• 2019

Nowadays in offshore industry there are emerging hazards with vague property such as act of terrorism, act of war, unforeseen natural disasters such as tsunami, etc. Therefore industry professionals such as offshore energy insurers, safety engineers and risk managers in order to determine the failure rates and frequencies for the potential hazards where there is no data available, they need to use an appropriate method to overcome this difficulty. Furthermore in conventional risk based analysis models such as when using a fault tree analysis, hazards with vague properties are normally waived and ignored. In other word in previous situations only a traditional probability based fault tree analysis could be implemented. To overcome this shortcoming fuzzy set theory is applied to fault tree analysis to combine the known and unknown data in which the pre-combined result will be determined under a fuzzy environment. This has been fulfilled by integration of a generic bow-tie based risk analysis model into the risk assessment phase of the Risk Management (RM) cycles as a backbone of the phase. For this reason Fault Tree Analysis (FTA) and Event Tree Analysis (ETA) are used to analyse one of the significant risk factors associated in offshore terminals. This process will eventually help the insurers and risk managers in marine and offshore industries to investigate the potential hazards more in detail if there is vagueness. For this purpose a case study of offshore terminal while coinciding with the nature of the Caspian Sea was decided to be examined.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.119-130
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• 2023

Among the various elements of probabilistic safety assessment (PSA), human failure events (HFEs) and their dependencies are major contributors to the quantification of risk of a nuclear power plant. Currently, the dependency among HFEs is reflected using a post-processing method in PSA, wherein several drawbacks, such as limited propagation of minimal cutsets through the fault tree and improper truncation of minimal cutsets exist. In this paper, we propose a method to model the HFE dependency directly in a fault tree using the if-then-else logic. The proposed method proved to be equivalent to the conventional post-processing method while addressing the drawbacks of the latter. We also developed a software tool to facilitate the implementation of the proposed method considering the need for modeling the dependency between multiple HFEs. We applied the proposed method to a specific case to demonstrate the drawbacks of the conventional post-processing method and the advantages of the proposed method. When applied appropriately under specific conditions, the direct fault-tree modeling of HFE dependency enhances the accuracy of the risk quantification and facilitates the analysis of minimal cutsets.

• 산업경영시스템학회지
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• 제13권21호
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• pp.43-50
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• 1990

Fault tree analysis(FTA) is available to the engineer for determining reliability of complex industrial safety system. Therefore quantitative aspects of FTA greatly multiply its power this paper proceeds of presenting the methodology of FTA, including an approach to constructing in fault tree. A working guide to the use of FTA for the purpose of cost/benefit determination in industrial safety system is given. Finally, an analytic method for uncertainty analysis of the top event of a complex system is described.

• 산업경영시스템학회지
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• 제23권54호
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• pp.155-165
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• 2000

The fault diagnosis is a systematic and unified method to find based on the observing data resulting in noises. This paper presents the fault prediction and diagnosis using fuzzy expert system technique to manipulate the uncertainties efficiently in predictive perspective. We apply a fuzzy event tree analysis to the computer system, and build up the fault prediction and diagnosis using fuzzy expert system that predicts and diagnoses the error of the system in the advance of error.

• Nuclear Engineering and Technology
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• 제53권2호
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• pp.498-508
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• 2021

Micro reactors are increasingly being considered for utilization as distributed power sources. Hence, the probabilistic safety assessment (PSA) of a direct supercritical-CO₂-cooled fast reactor, called micro modular reactor (MMR), was performed in this study; this reactor was developed using innovative design concepts. It adopted a modular design and passive safety systems to minimize site constraints. As the MMR is in its conceptual design phase, design weaknesses and valuable safety insights could be identified during PSA. Level 1 internal event PSA was carried out involving literature survey, system characterization, identification of initiating events, transient analyses, development of event trees and fault trees, and quantification. The initiating events and scenarios significantly contributing to core damage frequency (CDF) were determined to identify design weaknesses in MMR. The most significant initiating event category contributing to CDF was the transients with the power conversion system initially available category, owing to its relatively high occurrence frequency. Further, an importance analysis revealed that the safety of MMR can be significantly improved by improving the reliability of reactor trip and passive decay heat removal system operation. The findings presented in this paper are expected to contribute toward future applications of PSA for assessing unconventional nuclear reactors in their conceptual design phases.

• 한국정보처리학회논문지
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• 제4권6호
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• pp.1464-1480
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• 1997

분산 시스템은 높은 성능, 결함 허용성, 정보와 자원의 공유 등을 이룰 수 있는 환경을 제공한다. 그러나 분산 시스템 내에서 발생하는 사건과 상태들을 적절히 관리하지 못하면 이러한 장점의 혜택을 받을 수 없게 된다. 이러한 사건과 상태들은 성능 저하, 동작 오류, 수상한 행위 등의 징후가 될 수 있으므로 자세히 분석되어야 한다. 사건/상태를 적절히 관리하려면 이들을 명세하고 효율적으로 탐지할 수 있어야 한다. 본 논문에서는 사건/상태의 중앙 집중 탐지 알고리즘에 대해 설명한다. 다음 계층적 구조를 갖는 분산 시스템에서 이 탐지 알고리즘을 분산화 하는 방안에 대해 설명한다. 분산 알고리즘은 사건/상태 탐지 임무를 부임무들로 분해하는 과정과 부임무들을 적절한 노드들에 할당하는 과정으로 구성된다. 또 이 분산 탐지 알고리즘이 결함 허용성을 갖도록 하는 방안에 대해서도 설명한다.