• 제목/요약/키워드: Plant Operations

검색결과 367건 처리시간 0.021초

발전 플랜트 O&M을 위한 아키텍처 프레임워크 개념모델에 관한 연구 (Research on a Conceptual Model of Architecture Framework for Power Plant Operations & Maintenance(Q&M))

  • 임용택
    • 시스템엔지니어링학술지
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    • 제14권1호
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    • pp.83-88
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    • 2018
  • Engineering is a sector with more than three times the industrial effectiveness of manufacturing. In the domestic engineering life cycle, the Operations & Maintenance (O&M) phase is a relatively high level of technology. Based on accumulated knowledge of O&M phase, it is necessary to advance operating technology and expand overseas O&M market expenditure. This study is the early stage of knowledge-based power plant O&M service framework reference model. In this study, we propose a conceptual model of architecture framework for power plant O&M. We survey the architecture framework and reference model and propose conceptual model of architecture framework for power plant O&M. The conceptual model of architecture framework for power plant O&M consists of stakeholder, O&M scenario, O&M technology. In particular, the O&M technology is defined as the fourth industrial revolution intelligence information technology. We defined a meta model from the conceptual model to define the power plant O&M architecture framework. In the future, we intend to development an architecture framework from the conceptual model and meta model.

Algorithms and Planning Horizons for a One-Plant Multi-Retailer System

  • Lee, Sang-Bum
    • 한국경영과학회지
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    • 제13권1호
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    • pp.10-23
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    • 1988
  • This paper examines a deterministic, discrete-time, finite-horizon, production/distribution problem for a one-plant multi-retailer system. Production may occur at the plant in each time period. Customer demands at each retailer over a finite number of periods are known and must be met without backlogging. The plant as well as the retailers can serve as stocking points. The problem is to find a minimum-cost production/distribution schedule satisfying the known demands. We show that under a certain cost structure a nested policy is optimal, and present an efficient algorithm to find such an optimal policy. Planning horizon results and some computational saving schemes are also presented.

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국내 원전 발전정지사례 분석정보 시스템 개발

  • 이정운;박근옥
    • 한국경영과학회:학술대회논문집
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    • 대한산업공학회/한국경영과학회 1996년도 춘계공동학술대회논문집; 공군사관학교, 청주; 26-27 Apr. 1996
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    • pp.658-661
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    • 1996
  • Information that can be obtained from nuclear power plant trip cases is important for the efforts to reduce the trip occurrences. However, trip case reports, generally printed in documents, have shortcomings in using the contents. A database system called Information System of Trip Event Cases (INSTEC) is being developed to improve the use of trip information. INSTEC will provide the information obtained from the analysis of Korean nuclear power plant trips, such as component failures or human errors that induced the trips, problems contributed to the trips, and the sequence of unit events. In this study, in the process of INSTEC development, information analysis has been performed and a prototype of the system was developed. The prototype of INSTEC with user interface was presented to plant personnel to collect their opinion on INSTEC by using a questioninnaire. As results, it is confirmed that INSTEC would be helpful and useful for plant personnel to review the trip case information.

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발전소 시뮬레이터의 다이나믹 모델과 디스플레이 모델간 데이터전송 (Data Transporting between Dynamic Model and Display Model of Power Plant Simulator)

  • 김동욱
    • 한국시뮬레이션학회:학술대회논문집
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    • 한국시뮬레이션학회 1998년도 The Korea Society for Simulation 98 춘계학술대회 논문집
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    • pp.86-90
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    • 1998
  • The safety and reliability of nuclear power plant operations relies heavily on the plant operators ability to respond to various emergency situations. It has become standard industry practice to utilize simulators to improve the safety and reliability of nuclear power plants operations. The simulators built for Younggwang#3,4, which is the basic model of the Korean Nuclear Power Plant design, has been developed precisely for this purpose. Dynamic Model and Display Model are developed under US3(UNIX Simulation Software Support System) environment in simulator for Younggwang#3,4. Since these two models are developed under each own operating system, it is necessary to develop a method for transporting data between these two systems. This paper descirves communication environment between Dynamic Model and Display Model, and addresses a file generation method for the Display Model, which will be necessary for designing MMI of MCR(Main Control Room) in the furture.

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Vital area identification for the physical protection of NPPs in low-power and shutdown operations

  • Kwak, Myung Woong;Jung, Woo Sik
    • Nuclear Engineering and Technology
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    • 제53권9호
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    • pp.2888-2898
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    • 2021
  • Vital area identification (VAI) is an essential procedure for the design of physical protection systems (PPSs) for nuclear power plants (NPPs). The purpose of PPS design is to protect vital areas. VAI has been improved continuously to overcome the shortcomings of previous VAI generations. In first-generation VAI, a sabotage fault tree was developed directly without reusing probabilistic safety assessment (PSA) results or information. In second-generation VAI, VAI model was constructed from all PSA event trees and fault trees. While in third-generation VAI, it was developed from the simplified PSA event trees and fault trees. While VAIs have been performed for NPPs in full-power operations, VAI for NPPs in low-power and shutdown (LPSD) operations has not been studied and performed, even though NPPs in LPSD operations are very vulnerable to sabotage due to the very crowded nature of NPP maintenance. This study is the first to research and apply VAI to LPSD operation of NPP. Here, the third-generation VAI method for full-power operation of NPP was adapted to the VAI of LPSD operation. In this study, LPSD VAI for a few plant operational states (POSs) was performed. Furthermore, the operation strategy of vital areas for both full-power and LPSD operations was discussed. The LPSD VAI method discussed in this paper can be easily applied to all POSs. The method and insights in this study can be important for future LPSD VAI that reflects various LPSD operational states. Regulatory bodies and electric utilities can take advantage of this LPSD VAI method.

Operation optimization of auxiliary electric boiler system in HTR-PM nuclear power plant

  • Du, Xingxuan;Ma, Xiaolong;Liu, Junfeng;Wu, Shifa;Wang, Pengfei
    • Nuclear Engineering and Technology
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    • 제54권8호
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    • pp.2840-2851
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    • 2022
  • Electric boilers (EBs) are the backup steam source for the auxiliary steam system of high-temperature gas-cooled reactor nuclear power plants. When the plant is in normal operations, the EB is always in hot standby status. However, the current hot standby operation strategy has problems of slow response, high power consumption, and long operation time. To solve these problems, this study focuses on the optimization of hot standby operations for the EB system. First, mathematical models of an electrode immersion EB and its accompanying deaerator were established. Then, a control simulation platform of the EB system was developed in MATLAB/Simulink implementing the established mathematical models and corresponding control systems. Finally, two optimization strategies for the EB hot standby operation were proposed, followed by dynamic simulations of the EB system transient from hot standby to normal operations. The results indicate that the proposed optimization strategies can significantly speed up the transient response of the EB system from hot standby to normal operations and reduce the power consumption in hot standby operations, improving the dynamic performance and economy of the system.

제지공정의 모델예측제어 (Dynamic Matrix Control of Grade Change Operations in Paper Mills)

  • 박종호;여영구;강홍
    • 한국펄프종이공학회:학술대회논문집
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    • 한국펄프종이공학회 2004년도 추계학술발표집
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    • pp.212-220
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    • 2004
  • In this work the Dynamic Matrix Control method is applied to control the grade change operations in paper mills. Paper process trained by neural network regards a real-plant. The model obtained with operation data is used to achieve DMC. Results of simulations for DMC control of grade change operations are compared with plant operation data response. From the comparison, we can see that the proposed DMC method exhibits faster response for the grade change of paper and achieves stable steady-state.

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원자력발전소의 교대근무체계하에서 발생한 인적오류 시간 분포

  • 박근옥;이정운
    • 한국경영과학회:학술대회논문집
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    • 대한산업공학회/한국경영과학회 1996년도 춘계공동학술대회논문집; 공군사관학교, 청주; 26-27 Apr. 1996
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    • pp.266-269
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    • 1996
  • This paper describes the rotating shift system managed in Korean nuclear power plants and the retrospective analysis procedure of incidents induced by erroneous actions of plant personnel. It also describes the analysis results which include time distribution of erroneous actions occurred under the rotating shift system.

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Water Lubricated Guide Bearing with Self-aligning Segments

  • Oguma, Tadashi;Nakagawa, Naritoshi;Mikami, Makoto;Thantrong, Long;Kizaki, Yasumi;Takimoto, Fumio
    • International Journal of Fluid Machinery and Systems
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    • 제6권2호
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    • pp.49-55
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    • 2013
  • Water lubricated guide bearing was newly released and has been applied to actual hydro turbines with vertical shaft. As a result, they can have not only high bearing performance but environmental advantages in meeting the demand for reducing river pollution by oil leakage from oil lubricated guide bearing. The PTFE composite guide bearing was tested by experimental equipment operated under conditions similar to those of actual hydro turbines. Circumferential and axial tilting bearing segments help to improve the bearing performance and efficiency due to low friction loss in the bearing system. Furthermore, bearing cooling systems could be eliminated and maintenance periods could be extended, thus the initial investment and operating costs of the hydroelectric power plant are reduced.