• Title/Summary/Keyword: fault-effect tree

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Analysis of failure rate according to capacitor position of bidirectional converter (양방향 컨버터의 커패시터 위치에 따른 고장률 분석)

  • Kim, Ye-rin;Kang, Feel-soon
    • Journal of IKEEE
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    • v.23 no.1
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    • pp.261-265
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    • 2019
  • We analyze the failure rate change of a conventional bidirectional converter and a modified one which moves an output capacitor towards propulsion battery. We analysis of the circuit structural homogeneity and the difference between both converters, and confirm that the capacitor working voltage is reduced by changing the capacitor position. After obtaining the capacitor failure rate according to voltage stress factor and operating temperature, it is applied to the fault-tree of the bidirectional converter to obtain the overall failure rate of the converter. We analyzes the advantages and disadvantages of design changes by comparing and analyzing the failure rate and mean time between failures (MTBF) according to operating temperature and capacitance value.

An Integrative Method of FTA and FMEA for Software Security Analysis of a Smart Phone (스마트 폰의 소프트웨어 보안성 분석을 위한 FTA와 FMEA의 통합적 방법)

  • Kim, Myong-Hee;Toyib, Wildan;Park, Man-Gon
    • KIPS Transactions on Computer and Communication Systems
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    • v.2 no.12
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    • pp.541-552
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    • 2013
  • Recently software security of the smart phone is an important issue in the field of information science and technology due to fast propagation of smart technology in our life. The smart phone as the security critical systems which are utilizing in terminal systems of the banking, ubiquitous home management, airline passengers screening, and so on are related to the risk of costs, risk of loss, risk of availability, and risk by usage. For the security issues, software hazard analysis of smart phone is the key approaching method by use of observed failures. In this paper, we propose an efficient integrative framework for software security analysis of the smart phone using Fault Tree Analysis (FTA) and Failure Mode Effect Analysis (FMEA) to gain a convergence security and reliability analysis technique on hand handle devices. And we discuss about that if a failure mode effect analysis performs simpler, not only for improving security but also reducing failure effects on this smart device, the proposed integrative framework is a key solution.

A Case Study for Safety Analysis (안전성 분석에 대한 사례 연구)

  • Chang, Kwang-Chi;Lee, Key-Seo
    • Journal of the Korean Society for Railway
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    • v.7 no.3
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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.

FTA(Falut tree Analysis)기법을 이용한 이송용 로울러베어링 고장 진단

  • 배용환;이석희;이형국;최진원
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 1992.10a
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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.

A Study on the Safety Plan for a Train Control System (열차제어시스템의 안전계획 수립에 관한 연구)

  • Kim Jong-Ki;Shin Duc-Ko;Lee Key-Seo
    • Journal of the Korean Society for Railway
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    • v.9 no.3 s.34
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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.

The method of risk assessment by AMEA (AMEA을 활용한 위험성평가 방법)

  • Kim, Geon-Ho;Kwon, Sang-Myeon;Lee, Kang-Bok;Kim, Yoon-Sung;Lee, Jai-Won;Kang, Kyung-Sik
    • Journal of the Korea Safety Management & Science
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    • v.9 no.2
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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.

The Vulnerability Assessment of Hydro-pneumatic Suspension of Ground Combat Vehicles Using Vulnerable Area Method and DMEA (취약면적법과 DMEA를 활용한 지상전투차량 유공압 현가장치의 취약성 평가)

  • Nam, Myung Hoon;Park, Kang;Park, Woo Sung;Yoo, Chul
    • Korean Journal of Computational Design and Engineering
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    • v.22 no.2
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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.

Selection of Single Point Vulnerability through the Failure Mode Effect Analysis of Equipment in Newly built Nuclear Power Plant (신규원전의 기기별 고장분석을 통한 발전정지유발기기 선정)

  • Hyun, Jin-Woo;Yeom, Dong-Un;Song, Tae-Young
    • The Transactions of The Korean Institute of Electrical Engineers
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    • v.61 no.4
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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.

Implementation of DYLAM-3 to Core Uncovery Frequency Estimation in Mid-Loop Operation

  • Kim, Dohyoung;Chang hyun Chung;Moosung Jae
    • Nuclear Engineering and Technology
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    • v.30 no.6
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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.

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Sensitivity analysis of failure correlation between structures, systems, and components on system risk

  • Seunghyun Eem ;Shinyoung Kwag ;In-Kil Choi ;Daegi Hahm
    • Nuclear Engineering and Technology
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    • v.55 no.3
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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.