• Title/Summary/Keyword: Minimal cut sets

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A Systemetic Analysis of Gum Electro Automatic Overwrapping Machine Using FTA (FTA를 이용(利用)한 껌 자동포장기계(自動包裝機械) 고장(故障)의 체계적(體系的) 분석(分析))

  • Sin, Dong-Beom;Yun, Deok-Gyun
    • Journal of Korean Society for Quality Management
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    • v.12 no.1
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    • pp.45-58
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    • 1984
  • This paper performs a systematic analysis for failures in gum electro automatic overwrapping machine, using FTA technique. Data for failures which occurred from January, 1978 to June, 1983 are collected from machinery maintenance department at L. Confectionery Co. Ltd. In order to analyse them, COBOL computer program is performed because of a lot of time and effort. The minimal cut sets of the system failures are obtained from computer program. Through a set of analyses, the critical basic failures are found out.

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Computer-Aided Decision Analysis for Improvement of System Reliability

  • Ohm, Tai-Won
    • Journal of the Korea Safety Management & Science
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    • v.2 no.4
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    • pp.91-102
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    • 2000
  • Nowadays, every kind of system is changed so complex and enormous, it is necessary to assure system reliability, product liability and safety. Fault tree analysis(FTA) is a reliability/safety design analysis technique which starts from consideration of system failure effect, referred to as “top event”, and proceeds by determining how these can be caused by single or combined lower level failures or events. So in fault tree analysis, it is important to find the combination of events which affect system failure. Minimal cut sets(MCS) and minimal path sets(MPS) are used in this process. FTA-I computer program is developed which calculates MCS and MPS in terms of Gw-Basic computer language considering Fussell's algorithm. FTA-II computer program which analyzes importance and function cost of VE consists. of five programs as follows : (l) Structural importance of basic event, (2) Structural probability importance of basic event, (3) Structural criticality importance of basic event, (4) Cost-Failure importance of basic event, (5) VE function cost analysis for importance of basic event. In this study, a method of initiation such as failure, function and cost in FTA is suggested, and especially the priority rank which is calculated by computer-aided decision analysis program developed in this study can be used in decision making determining the most important basic event under various conditions. Also the priority rank can be available for the case which selects system component in FMEA analysis.

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Internal Event Level 1 Probabilistic Safety Assessment for Korea Research Reactor (국내 연구용원자로 전출력 내부사건 1단계 확률론적안전성평가)

  • Lee, Yoon-Hwan;Jang, Seung-Cheol
    • Journal of the Korean Society of Safety
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    • v.36 no.3
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    • pp.66-73
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    • 2021
  • This report documents the results of an at-power internal events Level 1 Probabilistic Safety Assessment (PSA) for a Korea research reactor (KRR). The aim of the study is to determine the accident sequences, construct an internal level 1 PSA model, and estimate the core damage frequency (CDF). The accident quantification is performed using the AIMS-PSA software version 1.2c along with a fault tree reliability evaluation expert (FTREX) quantification engine. The KRR PSA model is quantified using a cut-off value of 1.0E-15/yr to eliminate the non-effective minimal cut sets (MCSs). The final result indicates a point estimate of 4.55E-06/yr for the overall CDF attributable to internal initiating events in the core damage state for the KRR. Loss of Electric Power (LOEP) is the predominant contributor to the total CDF via a single initiating event (3.68E-6/yr), providing 80.9% of the CDF. The second largest contributor is the beam tube loss of coolant accident (LOCA), which accounts for 9.9% (4.49E-07/yr) of the CDF.

How to incorporate human failure event recovery into minimal cut set generation stage for efficient probabilistic safety assessments of nuclear power plants

  • Jung, Woo Sik;Park, Seong Kyu;Weglian, John E.;Riley, Jeff
    • Nuclear Engineering and Technology
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    • v.54 no.1
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    • pp.110-116
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    • 2022
  • Human failure event (HFE) dependency analysis is a part of human reliability analysis (HRA). For efficient HFE dependency analysis, a maximum number of minimal cut sets (MCSs) that have HFE combinations are generated from the fault trees for the probabilistic safety assessment (PSA) of nuclear power plants (NPPs). After collecting potential HFE combinations, dependency levels of subsequent HFEs on the preceding HFEs in each MCS are analyzed and assigned as conditional probabilities. Then, HFE recovery is performed to reflect these conditional probabilities in MCSs by modifying MCSs. Inappropriate HFE dependency analysis and HFE recovery might lead to an inaccurate core damage frequency (CDF). Using the above process, HFE recovery is performed on MCSs that are generated with a non-zero truncation limit, where many MCSs that have HFE combinations are truncated. As a result, the resultant CDF might be underestimated. In this paper, a new method is suggested to incorporate HFE recovery into the MCS generation stage. Compared to the current approach with a separate HFE recovery after MCS generation, this new method can (1) reduce the total time and burden for MCS generation and HFE recovery, (2) prevent the truncation of MCSs that have dependent HFEs, and (3) avoid CDF underestimation. This new method is a simple but very effective means of performing MCS generation and HFE recovery simultaneously and improving CDF accuracy. The effectiveness and strength of the new method are clearly demonstrated and discussed with fault trees and HFE combinations that have joint probabilities.

An approximate approach for Computing Fault-tree probabilities (Fault-tree 확률계산을 위한 근사적 방법)

  • Lee, Geun-Hui;Lee, Dong-Hyeong
    • Journal of Korean Society for Quality Management
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    • v.18 no.2
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    • pp.25-32
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    • 1990
  • This paper presents an approximate algorithm for computing Fault-tree probabilities. The method is essentially composed of three steps. In the first step, a Fault-tree is converted into a network form. In the second step, We change the network into a parallelized diagram. In the third step, the approximate fault-tree probability is calculated from the parallelized diagram. In this paper, in order to verify the method two hypothetical Fault-tree is used by examples. The results show that the method is very useful, even though it is an approximate technique, since it needs not to search the minimal cut sets and has the simple computing rontines.

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Fault Diagnosis of Screw type Air Compressor (스크루형 공기압축기의 고장진단)

  • Bae Yong-hwan
    • Journal of Advanced Marine Engineering and Technology
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    • v.28 no.7
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    • pp.1092-1100
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    • 2004
  • This paper describes the application of fault tree technique to analyze of compressor failure. Fault tree analysis technique involves the decomposition of a system into the specific form of fault tree where certain basic events lead to a specified top event which signifies the total failure of the system. In this research. fault trees for failure analysis of screw type air compressor are made. This fault trees are used to obtain minimal cut sets from system failure and system failure rate for the top event occurrence can be calculated. It is Possible to estimate air compressor reliability by using constructed fault trees through compressor failure example. It is Proved that FTA is efficient to investigate the compressor failure modes and diagnose system.

Failure Evaluation of The Digital Substation Based on Fault Tree Analysis (FTA에 기반한 디지털 변전소의 고장 분석)

  • Kim, Sung-Hun;Park, Ji-yeol;An, Yong-Ho;Kim, Seok-Kon;Lee, Seung-Hak;Lee, Dong-Ju
    • Proceedings of the KIEE Conference
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    • 2015.07a
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    • pp.553-554
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    • 2015
  • This paper presents the selection method of Minimal Cut Sets(MCS) for substation reliability evaluation. We used the Quality solution in order to model the FT for the substation equipment. Quantitative analysis is performed to estimate the probability of top event occurrence and unreliability of the substation component. In this result, it means that reliability indices which can be predict get electricity services and better maintenance in substation management.

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A Reliability Analysis of CVCS (노냉각수 제어계통의 신뢰도해석에 관한연구)

  • Chung Chan Lee;Byung Soo Lee;Chang Sun Kang
    • Nuclear Engineering and Technology
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    • v.15 no.1
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    • pp.11-22
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    • 1983
  • The reliability of the Chemical and Volume Control System has been analyzed in a pressurized water reactor. The boration failure was taken to be the top event for this reliability analysis. A detailed fault tree was constructed and the minimal cut sets were derived. It was computed that the unavailability of the Chemical and Volume Control System due to boration failure was 1.497$\times$10$^{-5}$ during plant operation. It was found that the reliability of boric acid transfer pumps were the most important factors in the availability of the Chemical and Volume Control System. As expected, human errors also introduce the high system unavilability.

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Diagnosis of Compressor Failure by Fault Tree Analysis (FTA기법을 이용한 콤프레서 고장진단)

  • 배용환;이석희;최진원
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.18 no.1
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    • pp.127-138
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    • 1994
  • The application of fault tree technique to the analysis of compressor failure is considered. The techniques involve the decomposition of the system into a form of fault tree where certain basic events lead to a specified top event which signifies the total failure of the system. In this paper, fault trees are made by using fault train of screw type air compressor failure. The fault trees are used to obtain minimal cut sets from the modes of system failure and, hence the system failure rate for the top event can be calculated. The method of constructing fault trees and the subsequent estimation of reliability of the system is illustrated through compressor failure. It is proved that FTA is efficient to investigate the compressor failure modes and diagnose system.

A Simple Approach to Calculate CDF with Non-rare Events in Seismic PSA Model of Korean Nuclear Power Plants (국내 원자력발전소 지진 PSA의 CDF 과평가 방지를 위한 비희귀사건 모델링 방법 연구)

  • Lim, Hak Kyu
    • Journal of the Korean Society of Safety
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    • v.36 no.5
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    • pp.86-91
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    • 2021
  • Calculating the scrutable core damage frequency (CDF) of nuclear power plants is an important component of the seismic probabilistic safety assessment (SPSA). In this work, a simple approach is developed to calculate CDF from minimal cut sets (MCSs) with non-rare events. When conventional calculation methods based on rare event approximations are employed, the CDF of industry SPSA models is significantly overestimated by non-rare events in the MCSs. Recently, quantification algorithms using binary decision diagrams (BDDs) have been introduced to prevent CDF overestimation in the SPSA. However, BDD structures are generated from a small part of whole MCSs due to limited computational memory, and they cannot be reviewed due to their complicated logic structure. This study suggests a simple approach for scrutinizing the CDF calculation based on whole MCSs in the SPSA system analysis model. The proposed approach compares the new results to outputs from existing algorithms, which helps in avoiding CDF overestimation.