• 제목/요약/키워드: System shutdown

검색결과 276건 처리시간 0.026초

마이크로 가스터빈 열병합 발전시스템 성능평가 (Performance Test of MGT Combined Heat & Power System)

  • 허광범;박정극;임상규
    • 유체기계공업학회:학술대회논문집
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    • 유체기계공업학회 2006년 제4회 한국유체공학학술대회 논문집
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    • pp.313-316
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    • 2006
  • As Decentralized Generation(DG) becomes more reliable and economically feasible, it is expected that a higher application of DG units would be interconnected to the existing grids. This new market penetration of DG technologies is linked to a large number of factors like technologies costs and performances, interconnection issues, safety, market regulations, environmental issues or grid connection constrains. Korea Electric Power Corporation (KEPCO) has researched performance characteristics of the 60k W class 1) basic start-up & shutdown operation analysis 2) interconnection test 3) MGT -absorption chiller-heater system in the local condition. Variations of heat recovery from exhaust gas has measured according to micro gas turbine output of 15, 30, 45, 60kW. From those results, the performance of the MGT-absorption chiller/heater system has been evaluated. The suggested strategy and experience for the evaluation of the distributed generation will be used for the introduction of other distributed generation technologies into the grid in the future.

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INSTRUMENTATION AND CONTROL STRATEGIES FOR AN INTEGRAL PRESSURIZED WATER REACTOR

  • UPADHYAYA, BELLE R.;LISH, MATTHEW R.;HINES, J. WESLEY;TARVER, RYAN A.
    • Nuclear Engineering and Technology
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    • 제47권2호
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    • pp.148-156
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    • 2015
  • Several vendors have recently been actively pursuing the development of integral pressurized water reactors (iPWRs) that range in power levels from small to large reactors. Integral reactors have the features of minimum vessel penetrations, passive heat removal after reactor shutdown, and modular construction that allow fast plant integration and a secure fuel cycle. The features of an integral reactor limit the options for placing control and safety system instruments. The development of instrumentation and control (I&C) strategies for a large 1,000 MWe iPWR is described. Reactor system modeling-which includes reactor core dynamics, primary heat exchanger, and the steam flashing drum-is an important part of I&C development and validation, and thereby consolidates the overall implementation for a large iPWR. The results of simulation models, control development, and instrumentation features illustrate the systematic approach that is applicable to integral light water reactors.

화력발전소 제어시스템 신뢰도 향상을 위한 전자카드 운영 방법 연구 (Research on the Maintenance Method to Improve the Reliability of Control System in Thermal Power Plant)

  • 신영진;박두용;김호열
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2006년도 심포지엄 논문집 정보 및 제어부문
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    • pp.240-242
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    • 2006
  • The inspection method, which is used to inspect the electronic system for the control system of the fossil-powered thermal power plant, has the technical restrictions based on its primary application area, whereas the reliability is requested more and more by the plant operators to minimize the shutdown of a plant. This paper reviews the inspection methods currently used by the thermal power plant and how to adopt the condition based maintenance to increase the availability of power plant.

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교류전동기 제어시스템을 위한 실시간 고장검출진단 (Real-time FDI Schemes for AC Motor Control Systems)

  • 박태건;류지수;이기상
    • 전력전자학회:학술대회논문집
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    • 전력전자학회 2002년도 전력전자학술대회 논문집
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    • pp.77-81
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    • 2002
  • In many high performance engineering systems such as automated production system and transportation systems, AC-servo drives are employed as the most Important driving parts. And the faults of servo drives result in overall system performance deterioration or an unscheduled shutdown In critical situations. The real-time fault detection and isolation(FDI) scheme Is very useful to prevent them and to guarantee the desired reliability of the overall system. In this paper, the FDI schemes which can be applied to AC servo drives are introduced and some new results are presented.

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Design of Intelligent Insulation Degradation Sensor

  • Kim, Yi-Gon
    • International Journal of Fuzzy Logic and Intelligent Systems
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    • 제2권3호
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    • pp.191-193
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    • 2002
  • Insulation aging diagnosis system provides early warning in regard to electrical equipment defects. Early warning is very important in that it can avoid great losses resulting from unexpected shutdown of the production line. For solving this problem, many researchers proposed a method that diagnose power plant by using partial discharge. In this paper, we design the intelligent sensor to diagnose insulation degradation state that uses a Microprocessor and Al. Proposed sensor has MCU that is used to diagnose insulation degradation and communicate with main IDD system. And we use a fuzzy model to diagnose insulation degradation.

Application of Coupled Reactor Kinetics Method to a CANDU Reactor Kinetics Problem.

  • Kim, Hyun-Dae-;Yeom, Choong-Sub;Park, Kyung-Seok-
    • 한국에너지공학회:학술대회논문집
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    • 한국에너지공학회 1994년도 추계학술발표회 초록집
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    • pp.141-145
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    • 1994
  • A computer code for solving the 3-D time-dependent multigroup neutron diffusion equation by a coupled reactor kinetics method recently developed has been developed and for evaluating its applicability in CANDU transient analysis applied to a 3-D kinetics benchmark problem which reveals non-uniform loss of coolant accident followed by an asymmetric insertion of shutdown devices. The performance of the method and code has been compared with the CANDU design code, CERBERUS, employing a finite difference improved quasistatic method.

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Performance measurement of safety-critical systems based on ordinary differential equations and Petri nets: A case study of nuclear power plant

  • Nand Kumar Jyotish;Lalit Kumar Singh;Chiranjeev Kumar
    • Nuclear Engineering and Technology
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    • 제55권3호
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    • pp.861-869
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    • 2023
  • This article proposes a novel approach to measure the performance of Safety-Critical Systems (SCS). Such systems contain multiple processing nodes that communicate with each other is modeled by a Petri nets (PN). The paper uses the PN for the performance evaluation of SCS. A set of ordinary differential equations (ODEs) is derived from the Petri net model that represent the state of the system, and the solutions can be used to measure the system's performance. The proposed method can avoid the state space explosion problem and also introduces new metrics of performance, along with their measurement: deadlock, liveness, stability, boundedness, and steady state. The proposed technique is applied to Shutdown System (SDS) of Nuclear Power Plant (NPP). We obtained 99.887% accuracy of performance measurement, which proves the effectiveness of our approach.

공정의 안전 검증을 위한 PLC 모듈 개발 (Development of PLC modules for the safety verification of chemical processes)

  • 정상헌;이광순;문일
    • 제어로봇시스템학회논문지
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    • 제2권1호
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    • pp.53-59
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    • 1996
  • An automatic verification method has been studied to determine the safety and operability of programmable logic controller (PLC) based systems. For the systematic and efficient verification, we have developed a conversion method from relay ladder logic (RLL) to the verification system description. RLL is a common representation used to document PLC programs for the sequential logic of the system such as the safety interlocks and the startup/shutdown procedures. Once the modules are developed, complex RLLs can be represented by the combination of modules. As a result we can verify complex PLC systems using the verification method including RLL modules. The developed modules are used to verify alarm systems and show that the method is valid.

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RELAP5/MOD3 Assessment Against a ROSA-IV/LSTF Loss-of-RHRS Experiment

  • Park, Chul-Jin;Han, Kee-Soo;Lee, Cheol-Sin;Kim, Hee-Cheol;Lee, Sang-Keun
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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    • pp.745-750
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    • 1996
  • An analysis of a loss of residual heat removal system (RHRS) event during midloop operation after reactor shutdown was performed using the RELAP5/MOD3 thermal-hydraulic computer code. The experimental data of a 5% cold leg break test conducted at the ROSA-IV Large Scale Test Facility (LSTF) to simulate a main coolant pump shaft seal removal event during midloop operation of a Westinghouse-type PWR were used in the analysis. The predicted core boiling time and the peak primary system pressure showed good agreements with the measured data. Some differences between the calculational results and the experimental results were, however, found in areas of the timing of loop seal clearing and the temperature distribution in a pressurizer. Other calculational problems identified were discussed as well.

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P&S를 활용한 발전용 SOVR의 모델링과 동특성 해석 (Modeling and Simulation for Dynamic Behaviors of SOVR for Electric Power Plant)

  • 노태정
    • 제어로봇시스템학회:학술대회논문집
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    • 제어로봇시스템학회 2000년도 제15차 학술회의논문집
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    • pp.203-203
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    • 2000
  • The P&S(Power Plant Simulation System) is a powerful simulation software system for the dynamic behavior of power plants. The P&S module libraries provide plant models with higher flexibility of dynamic simulations for process and control designs. The P&S software was effectively available for PCS based on Linux and modem workstations based on Unix. The P&S was applied for simulating the dynamic behaviors of the SOVR(Supercritical Once-Through Variable Pressure Reheater) according to the operations such as stan-up, shutdown, load following, load change and trip in order to obtain an optimal operation procedure for Unit 5/6 of Taeahn fossil power plant consisted of SOVRs and steam turbines.

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