• 제목/요약/키워드: Plant maintenance

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The consideration of the electronic cooling device for outside panel (옥외 자립형 PANEL에 적용한 전자냉각장치 고찰)

  • Ok, Yeon-Ho;Lim, Jae-Il;Park, Ji-Kun;Kwak, Won-Ku;Lee, Jae-Heung;Kim, Byung-Ki
    • Proceedings of the KIEE Conference
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    • 2008.07a
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    • pp.353-354
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    • 2008
  • 옥외 현장에 설치되어 있는 PANEL은 하절기에 내부 온도가 높아져 PANEL 내부에 설치되어 있는 제어장치의 정상 동작을 방해 할 수 있다. 실제로 하절기 오후 $2{\sim}3$시경 PANEL 내부의 온도는 약 $60{\sim}75^{\circ}C$ 정도의 고온을 유지한다. 근래에는 현장 PANEL 내부에 PLC 및 컨트롤러등 전자화된 제어 장치의 설치 비중이 증가하고 있고 대부분의 컨트롤러 사용 온도는 약 $0{\sim}55^{\circ}C$ 이므로 하절기 고온 상태에서 정상적인 동작을 기대하기는 어렵다. 본 논문에서는 옥외 자립형 PANEL의 냉각 장치를 개발하여 운영하고 그 효과를 분석, 검토함으로써 하절기 고온 상태에서도 안정적으로 설비가 정상 동작하기 위한 방안 제시를 주요 목적으로 한다.

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Development of Maintenance Effectiveness Monitoring Program based on Design Characteristics for New Nuclear Power Plant (신규원전의 설계특성 기반 정비효과성감시 프로그램 개발)

  • Yeom, Dong-Un;Hyun, Jin-Woo;Song, Tae-Young
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.8 no.1
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    • pp.25-32
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    • 2012
  • Korea Hydro & Nuclear Power Co. (KHNP) has developed and implemented the maintenance effectiveness monitoring (MR) programs for the operating nuclear power plants. The MR program is developed by reflecting design characteristics of the operating nuclear power plants to monitor the plant performance for improving the safety and reliability. Recently, KHNP has built a new nuclear power plant, and developed the MR program to establish the advanced maintenance system by reflecting unique design characteristics based on the OPR1000 standard model. So, the MR program developed in this study has another characteristics in comparison with the OPR1000 standard model, and we will verify the suitability of the MR program through evaluating initial performance of the plant. The safety and reliability of the new plant will be improved by developing and implementing the MR program.

A Development of Image Transfer Remote Maintenance Monitoring System for Hand Held Device (휴대용 화상전송 원격정비 감시시스템의 개발)

  • Kim, Dong-Wan;Park, Sung-Won
    • The Transactions of the Korean Institute of Electrical Engineers P
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    • v.58 no.3
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    • pp.276-284
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    • 2009
  • In this paper, we develop the image transfer remote maintenance monitoring system for hand held device which can compensate defects of human mistake. The human mistakes always happen when the worker communicate information each other to check and maintenance the equipment of the power plant under bad circumstance such as small place and long distance in power plant. A worker couldn't converse with other when in noisy place like Power plant. So, we make some hand device for handy size and able to converse in noisy place. The developed system can have improvement of productivity through increasing plant operation time. And developed system is composed of advanced H/W(hard ware) system and S/W(soft ware)system. The H/W system consist of media server unit, communication equipment with hand held device, portable camera, mike and head set. The advanced s/w system consist of data base system, client pc(personal computer) real time monitoring system which has server GUI(graphic user interface) program, wireless monitoring program and wire ethernet communication program. The client GUI program is composed of total solution program as pc camera program, and phonetic conversation program etc.. We analyzed the required items and investigated applicable part in the image transfer remote maintenance monitoring system with hand held device. Also we investigated linkage of communication protocol for developed prototype, developed software tool of two-way communication and realtime recording skill of voice with image. We confirmed the efficiency by the field test in preventive maintenance of plant power.

Development of the Preventive Maintenance Template for Static Exciter in the Nuclear Power Plant (원자력발전소 정지형 여자기의 예방정비기준(PMT) 개발)

  • Chin, Soo-Hwan;Park, Jin-Youb;Hong, Young-Hee
    • Journal of Energy Engineering
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    • v.20 no.2
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    • pp.154-162
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    • 2011
  • PMT(Preventive Maintenance Template) is a standardized maintenance program that describes maintenance items & period as operation condition to increase component reliability at the component level. The existing maintenance programs are focused on time based maintenance to inspect and repair component depend on fixed period. But recently, we have developed advanced maintenance program(named PMT) to increase reliability and optimize maintenance program of the plant significant component. This paper presents how to develop the PMT for nuclear power plant's static exciter.

Development of a New Prediction Alarm Algorithm Applicable to Pumped Storage Power Plant (양수발전 설비에 적용 가능한 새로운 고장 예측경보 알고리즘 개발)

  • Dae-Yeon Lee;Soo-Yong Park;Dong-Hyung Lee
    • Journal of Korean Society of Industrial and Systems Engineering
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    • v.46 no.2
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    • pp.133-142
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    • 2023
  • The large process plant is currently implementing predictive maintenance technology to transition from the traditional Time-Based Maintenance (TBM) approach to the Condition-Based Maintenance (CBM) approach in order to improve equipment maintenance and productivity. The traditional techniques for predictive maintenance involved managing upper/lower thresholds (Set-Point) of equipment signals or identifying anomalies through control charts. Recently, with the development of techniques for big analysis, machine learning-based AAKR (Auto-Associative Kernel Regression) and deep learning-based VAE (Variation Auto-Encoder) techniques are being actively applied for predictive maintenance. However, this predictive maintenance techniques is only effective during steady-state operation of plant equipment, and it is difficult to apply them during start-up and shutdown periods when rises or falls. In addition, unlike processes such as nuclear and thermal power plants, which operate for hundreds of days after a single start-up, because the pumped power plant involves repeated start-ups and shutdowns 4-5 times a day, it is needed the prediction and alarm algorithm suitable for its characteristics. In this study, we aim to propose an approach to apply the optimal predictive alarm algorithm that is suitable for the characteristics of Pumped Storage Power Plant(PSPP) facilities to the system by analyzing the predictive maintenance techniques used in existing nuclear and coal power plants.

The Application Analysis of Power System Stabilizer in Hydraulic power plant (전력계통안정화장치(PSS) 수력발전소 적용분석)

  • Ok, Yeon-Ho;Lim, Jae-Il;Park, Ji-Kun;Kwak, Won-Ku;Lee, Kwang-Yeon
    • Proceedings of the KIEE Conference
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    • 2007.11b
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    • pp.63-65
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    • 2007
  • Recently with increase consumption of electric power, the scale of the electric system becomes bigger and complex. Then, it is increasing the hardship in the operation of electric system and the continuance of stability. Especially, as the differences between demand and supply in electric power keeping low frequency oscillating attenuation from electric power have been very important in the continuance part of stability. The more control time of electricity system is getting faster with digitalization the more stability of electricity system is getting worse. As solutions of these problems, by establishing Power System Stabilizing Controller putting PSS output signal and putting damping to vibration of the rotor at generators's AVR in area where is oscillated, We are willing to contribute the electricity system by holding in generator output vibration.

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Failure Data Base for Reliability-Based Maintenance for a Power Plant (신뢰도 기반 발전플랜트 정비를 위한 고장 데이터베이스 구축 방법)

  • Kim, Myungbae;Kim, Taehoon;Kim, Hyungchul;Lim, Shinyoung
    • Plant Journal
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    • v.12 no.2
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    • pp.31-35
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    • 2016
  • A method of failure data management for Reliability-Centered Maintenance was shown for a boiler feedwater pump of a power plant. The major part of it is an analysis of failure mode, failure cause, and failure effects, which is the main component of a failure data base like OREDA(Offshore Reliability Data). Case study shows main element of the preventive maintenance planning such as the maintenance period can be statistically determined from the failure data.

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Decision-making Method of Optimum Inspection Interval for Plant Maintenance by Genetic Algorithms (유전 알고리즘에 의한 플랜트 보전을 위한 최적검사기간 결정 방법론)

  • 서광규;서지한
    • Journal of Korean Society of Industrial and Systems Engineering
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    • v.26 no.2
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    • pp.1-8
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    • 2003
  • The operation and management of a plant require proper accounting for the constraints coming from reliability requirements as well as from budget and resource considerations. Most of the mathematical methods to decide the inspection time interval for plant maintenance by reliability theory are too complicated to be solved. Moreover, the mathematical and theoretical models are not usually cases in the practical applications. In order to overcome these problems, we propose a new the decision-making method of optimal inspection interval to minimize the maintenance cost by reliability theory and genetic algorithm (GA). The most merit of the proposed method is to decide the inspection interval for a plant machine of which failure rate $\lambda$(t) conforms to any probability distribution. Therefore, this method is more practical. The efficiency of the proposed method is verified by comparing the results obtained by GA-based method with the inspection model haying regular time interval.

Deterioration Evaluation for Industrial Pipeline by Sectionalizing (산업시설 배관의 섹션화에 의한 노후도 평가)

  • Min, Hyuk-Ki;Kim, Sang-Bum;Kim, Byung-Woo;Kim, Hyoung-Ki;Park, Yool
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.28 no.3
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    • pp.123-130
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    • 2016
  • This study introduced deterioration evaluation item and criteria that could be applied to industrial facilities with the most widely used carbon steel pipe installed for ordinary piping (KSD 3507). Experimental industrial pipes were evaluated with pipe sectionalizing method combined with the established evaluation item and criteria to measure and manage semi-continuously for overall piping system. After applying outcomes from this study to a plant of incineration facility, a 42% saving in repairing and remodeling cost was achieved.

Optimization of preventive maintenance of nuclear safety-class DCS based on reliability modeling

  • Peng, Hao;Wang, Yuanbing;Zhang, Xu;Hu, Qingren;Xu, Biao
    • Nuclear Engineering and Technology
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    • v.54 no.10
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    • pp.3595-3603
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    • 2022
  • Nuclear safety-class DCS is used for nuclear reactor protection function, which is one of the key facilities to ensure nuclear power plant safety, the maintenance for DCS to keep system in a high reliability is significant. In this paper, Nuclear safety-class DCS system developed by the Nuclear Power Institute of China is investigated, the model of reliability estimation considering nuclear power plant emergency trip control process is carried out using Markov transfer process. According to the System-Subgroup-Module hierarchical iteration calculation, the evolution curve of failure probability is established, and the preventive maintenance optimization strategy is constructed combining reliability numerical calculation and periodic overhaul interval of nuclear power plant, which could provide a quantitative basis for the maintenance decision of DCS system.