• 전기전자학회논문지
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• 제23권1호
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• pp.261-265
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• 2019

기존 양방향 컨버터와 출력 커패시터를 추진용 배터리 쪽으로 이동시킨 양방향 컨버터의 고장률 변화를 분석한다. 두 컨버터의 회로 구조적 동일성과 차이점을 분석하여 커패시터 위치 변경으로 동작전압이 저감됨을 확인한다. 전압스트레스 인자와 동작온도에 따른 커패시터 부품 고장률을 구하고 양방향 컨버터의 고장나무에 적용하여 컨버터 전체 고장률을 구한다. 동작온도와 커패시턴스 값에 따른 고장률과 평균고장시간을 비교 분석하여 설계 변경으로 인한 장 단점을 분석한다.

• 정보처리학회논문지:컴퓨터 및 통신 시스템
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• 제2권12호
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• pp.541-552
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• 2013

최근 우리 생활에 스마트 기술의 빠른 전파 때문에 정보 과학 및 기술 분야에 있어서는 스마트 폰의 소프트웨어 보안성이 중요한 이슈가 되고 있다. 보안성 중요 시스템인 스마트 폰은 은행 서비스, 유비쿼터스 홈 관리, 항공 고객의 검색 등의 서비스 시스템에 이용되기 때문에 비용의 리스크, 손실의 리스크, 이용가능 리스크, 그리고 사용상의 리스크에 관련 되어 있다. 스마트 폰의 보안성 이슈는 이들의 관찰된 고장들을 사용하여 소프트웨어 장애 분석을 하는 것이 핵심 접근 방법이다. 본 연구에서는 손으로 조작하는 디바이스들의 수렴하는 보안성과 신뢰성 분석 기법을 얻기 위해서 결함 트리 분석 (FTA)와 고장 모드 효과 분석(FMEA)을 사용하여 스마트 폰의 소프트웨어 보안성 분석을 위한 하나의 유효한 통합적 프레임 워크를 제안한다. 그리고 만약 하나의 고장 모드 효과 분석이 더욱 더 간단해지면 스마트 디바이스들의 보안성 개선뿐만 아니라 고장효과 의 감소를 위해서 제안된 통합적인 프레임 워크는 핵심 해법이 됨을 논의한다.

• 한국철도학회논문집
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• 제7권3호
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• pp.251-258
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• 2004

A systematic methodology to determine safety requirements for railway signalling system and safety requirement allocation into system are presented. THR concept is used for as an interface between Risk Analysis to be performed by railway operator and System Design Analysis by the supplier. This approach is based on Signalling Safety Standard EN50129 by CENELEC.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 1992년도 추계학술대회 논문집
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• pp.325-329
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• 1992

The development of automatic production system have required intelligent diagnostic and monitoring function to repair system failure and reduce production loss by the failure. In order to perform accurate functions of intelligent system, inference about total system failure and fault analysis due to each mechanical component failures are required. Also the solution about repair and maintenance can be suggested from these analysis results. Generally, bearing is a essential mechanical component in the machinery. The bearing failure is caused by lubricant system failure, metallurgical defficiency, mechanical condition(vibration overloading misalignment), environmental effect. This study described roller bearing fault train due to stress variation and metallurgical defficiency from lubricant failure by using FTA.

• 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.

• 대한안전경영과학회지
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• 제9권2호
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• pp.97-111
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• 2007

In risk assessment, there are several methods such as Safety Review, Checklist, FMEA(Failure Mode and Effect Analysis), FTA(Fault Tree Analysis), ETA (Event Tree Analysis) etc, however, the level of accident is indentified by the probability of accident and severity resulting from accident which used widely in assessing accidents and disasters. In this paper, the risk assessment method to decide the level of risk will be introduced by using severity, frequency and detection according to accident theory.

• 한국CDE학회논문집
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• 제22권2호
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• pp.141-149
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• 2017

Vulnerability assesses the loss of major performance functions of GCV (Ground Combat Vehicles) when it is hit by enemy's shell. To decide the loss of major functions, it is determined what effects are on the performance of GCV when some components of GCV are failed. M&S (Modeling and Simulation) technology is used to vulnerability assessment. The hydro-pneumatic suspension is used as a sample part. The procedures of vulnerability assessment of the hydro-pneumatic suspension are shown as follows: 1) The components of the suspension are defined, and shot lines are generated evenly around the part. 2) The penetrated components are checked by using the penetration equation. 3) The function model of the suspension is designed by using IDEF0. 4) When the failure of the critical components of the suspension happens, its effect on the function of the suspension can be estimated using DMEA (Damage Mode and Effects Analysis). 5) The diagram of FTA (Fault Tree Analysis) is designed by exploiting DMEA. 6) The damage probability of the suspension is calculated by using FTA and vulnerable area method. In this paper, SLAP (Shot Line Analysis Program) which was developed based on COVART methodology. SLAP calculates the damage probability and visualizes the vulnerable areas of the suspension.

• 전기학회논문지
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• 제61권4호
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• pp.509-512
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• 2012

For decreasing an unexpected shutdown of Nuclear Power Plants, Korea Hydro & Nuclear Power co.(KHNP) has developed Single Point Vulnerability(SPV) of NPPs since 2008. SPV is the equipment that cause reactor shutdown & turbine trip or more than 50% power rundown due to its malfunction. Newly built Nuclear Power Plants need to develop the SPV list, so performed the job which analyse equipment failure effect for SPV selection for 1 year. To develop this, Failure Mode Effect Analysis(FMEA) and Fault Tree Analysis(FTA) methods are used. As results of this analysis, about 900 equipment are selected as SPV. Thereafter those are going to be applied to Nuclear Power Plants to enhance equipment reliability.

• Nuclear Engineering and Technology
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• 제30권6호
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• pp.531-540
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• 1998

The DYLAM-3 code which overcomes the limitation of event tree/fault tree was applied to LOOP (Loss of Off-site Power) in the mid-loop operation employing HEPs (Human Error Probabilities) supplied by the ASEP (Accident Sequence Evaluation Program) and the SEPLOT (Systematic Evaluation Procedure for Low power/shutdown Operation Task) procedure in this study. Thus the time history of core uncovery frequency during the mid-loop operation was obtained. The sensitivity calculations in the operator's actions to prevent core uncovery under LOOP in the mid-loop operation were carried out. The analysis using the time dependent HEP was performed on the primary feed & bleed which has the most significant effect on core uncovery frequency. As the result, the increment of frequency is shown after 200 minutes duration of simulation conditions. This signifies the possibility of increment in risk after 200 minutes. The primary feed & bleed showed the greatest impact on core uncovery frequency and the recovery of the SCS (Shutdown Cooling System) showed the least impact. Therefore the efforts should be taken on the primary feed & bleed to reduce the core uncovery frequency in the mid-loop operation. And the capability of DYLAM-3 in applying to the time dependent concerns could be demonstrated.

• 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.