• Proceedings of the Korean Nuclear Society Conference
• /
• 2002.10a
• /
• pp.193.2-193
• /
• 2002

• JOURNAL OF ELECTRICAL WORLD
• /
• s.261
• /
• pp.70-76
• /
• 1998

철도분야에서의 전기$\cdot$신호설비 고장은 열차의 정상운행에 차질을 일으켜 사회적으로 커다란 영향을 끼치게 되므로 설비의 유지관리를 위해서는 많은 노력이 필요하다. 또 이러한 보전작업에는 철도 설비가 널리 산재되어 있기 때문에 이동을 수반하는 작업, 열차가 통과하지 않는 야간 작업, 만일의 경우 위험을 수반하는 작업 등, 이 분야 특유의 작업이 있다. 한편 보전작업에 종사하는 기술자는 해마다 줄어들고 있으며 앞으로 젊은 근로자의 부족은 더욱더 심해질 것으로 보인다. 그러한 이유로 설비보전의 자력화, 미연의 고장방지, 고장의 조기복구와 재발방지를 목표로 지금까지 사람의 손에 의지해 오던 설비보전을 기계화하고 자동화하는 시스템을 개발하게 되었다. 이 시스템은 대상설비에 따라 다음의 3가지 시스템으로 분류된다. $\cdot$신호설비 보전시스템 $\cdot$변전$\cdot$수배전설비 보전시스템$\cdot$연선전기설비 보전시스템 이들시스템에 공통적인 주요 특징을 들면 아래와 같다. (1)사고를 미연에 방지하고 사고원인을 규명 이벤트발생 전후의 변화나 중장기트렌드를 원격감시할 수 있다. (2)시스템의 변경$\cdot$증설이 용이 인텔리전트단말에 의하여 처리를 계층화하였기 때문에 빌딩블록식으로 시스템을 확장할 수 있다. (3)경제적인 시스템 필드 네트워크의 채용으로 공사비를 삭감할 수 있다.

• Journal of the Korean Society for Aeronautical & Space Sciences
• /
• v.50 no.4
• /
• pp.259-267
• /
• 2022

The existing method of deriving the fail-safe design requirements for the domestic developed rotary-wing aircraft system may miss the factors that cause critical system function failures, when being applied to the latest integrated avionics system. It is because the existing method analyzes the severity effect of the failures caused by a single item. To solve the issue, we present a systematic analysis procedure for deriving fail-safe design requirements of system architecture by utilizing functional hazard assessment and development assurance level analysis of SAE ARP4754A, international standard for complex system development. To demonstrate that our proposed procedure can be a solution for the aforementioned issue, we set up experimental environments that include common factors that can cause critical function failures of a system, and we conducted a cross-validation with the existing method. As a result, we showed that the proposed procedure can identify the potential critical common factors that the existing method have missed, and that the proposed procedure can derive fail-safe design requirements to control the common factors.

• Journal of Korean Society for Quality Management
• /
• v.46 no.2
• /
• pp.327-338
• /
• 2018

Purpose: A risk evaluation procedure is proposed for common failure causes in FMEA(Failure Mode and Effects Analysis). The conventional FMEA does not provide a proper means to compare common failure causes with other failure causes. This research aims to develop a risk evaluation procedure in FMEA where common failure causes and other failure causes exist together. Methods: For each common failure cause, the effect of each combination of its resulting failures is recommended to be reevaluated considering their interactive worsening effect. And the probability that each combination of failures is incurred by the same common cause is also considered. Based on these two factors, the severity of each common cause is determined. Other procedures are similar to the conventional method. Results: The proposed procedure enables to compare and prioritize every failure cause. Thus, the common causes, each of which incurring two or more failures, and other causes, each of which is corresponding to one failure, can be fairly compared. Conclusion: A fair and proper way of comparing the common failure causes and other causes is provided. The procedure is somewhat complicated and requires more works to do. But it is worth to do.

• Transactions of the Korean Society of Pressure Vessels and Piping
• /
• v.10 no.1
• /
• pp.51-55
• /
• 2014

Based on the results of Probabilistic Safety Assessment(PSA) for a Nuclear Power Plant (NPP), Common Cause Failure(CCF) events have been recognized as one of the main contributors to the risk. Also, the CCF data and estimation method used in domestic PSA models have been pointed out as an issue with respect to the quality. The existing method of MGL and non-staggered testing even widely used were considered conservative in estimating the safety and had a limited capability in uncertainty analyses. Therefore, this paper presents the CCF estimation using a new generic data source and Alpha factor method. The analyses showed that Alpha factor and staggered method are effective in estimating the CCF contribution and risk insights of reference plant. This method will be a common bases for the optimization of new design for the construction plants as well as for the updating of safety assessment on the operating nuclear power plants.

• IE interfaces
• /
• v.25 no.4
• /
• pp.405-415
• /
• 2012

The reliability performance measures for low and high or continuous demand modes of operation of safety instrumented systems(SISs) are examined and compared by analyzing the official definitions in IEC 61508 standard. This paper also presents a status of common cause factor(CCF) models used in IEC 61508 and problems relating CCF modelling are discussed and ideas to solve these ones are suggested. An example with mixed M-out-of-N architecture is carried out to illustrate the proposed methods.

• IE interfaces
• /
• v.25 no.4
• /
• pp.382-392
• /
• 2012

Reactor protection system to keep nuclear safety and operational economy of plants requires high reliability. Such a high reliability of the system can be achieved through the redundant design of components. However, common cause failures of components reduce the benefits of redundant design. Thus, the common cause failure analysis, to accurately calculate the reliability of the reactor protection system, is carried out using alpha-factor model. Analysis results to 24 operating months are that 1) the system reliability satisfies the reliability goal of EPRI-URD and 2) the common cause failure contributes 90% of the system unreliability. The uncertainty analysis using alpha factor parameters of 0.05 and 0.95 quantile values shows significantly large difference in the system unreliability.

• Journal of Korean Society for Quality Management
• /
• v.39 no.2
• /
• pp.320-328
• /
• 2011

This research proposes comprehensive models for analyzing common cause failures (CCF) due to cumulative shocks and to assess system reliability under the CCF. The proposed cumulative shock models are based on the binomial failure rate (BFR) model. Six kinds of models are proposed so as to explain diverse cumulative shock phenomena. The models are composed of the initial failure probability, shape parameter, and the total shock number. Some parameters of the proposed models can not be explicitly estimated, so we adopt the Expectation-maximization (EM) algorithm in order to obtain the maximum likelihood estimator (MLE) for the parameters. By estimating the parameters for the cumulative shock models, the system reliability with CCF can be assessed sequentially according to the number of cumulative shocks. The result can be utilizes in dynamic probabilistic safety assessment (PSA), aging studies, or risk management for nuclear power plants. Replacement or maintenance policies can also be developed based on the proposed model.

• Proceedings of the Korea Information Processing Society Conference
• /
• 2014.04a
• /
• pp.595-598
• /
• 2014

원전 디지털 계측제어시스템에서 공통원인고장(Common cause failure)의 발생 가능성이 증가함에 따라 이를 방지하기 위해 프로그래머블 논리소자(Field Programmable Gate Array)를 이용한 제어기가 개발되어 활용되고 있다. 그러나, FPGA-기반의 제어기를 구현하는데 사용되는 하드웨어 기술 언어는 그래픽 언어를 이용한 PLC 기반의 개발을 하던 대부분의 원전 계측제어 엔지니어에게 친숙하지 않아 제어기의 구현에 어려움이 있다. 따라서 엔지니어에게 친숙한 그래픽 언어를 이용하여 FPGA 용 제어 프로그램을 작성할 수 있는 통합개발환경이 필요하다. 본 논문에서 구현한 VerilogLinker 는 제어프로그램의 개발을 위한 통합개발환경의 일부로 통합개발환경을 이용한 제어 프로그램의 개발과정 중에서 생성된 Verilog 파일을 FPGA 공급자가 제공하는 상용 소프트웨어인 Libero SoC 와 연결하는 기능을 제공한다.

• Proceedings of the KSR Conference
• /
• 2008.11b
• /
• pp.255-262
• /
• 2008

The railway is required to be highly reliable, which carries a lot of passenger and baggage. Presently, the reliability prediction method is based on independent failure. If the common cause failure affecting many components simultaneously in a system occurs, the system has seriously an aptitude to be broken out. Therefore, for raising the reliability of the railway power system, it is introduced that the analysis is conducted to use the common cause failure. The common cause failure is modeled and is combined with independent failure. Furthermore in order to examine the method, it is applied to the railway power substation. If this method is used to the power system, the reliability of the railway power system will be highly improved.