• Title/Summary/Keyword: power plant modeling

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Intelligent Control of Nuclear Power Plant Steam Generator Using Neural Networks (신경회로망을 이용한 원자력발전소 증기발생기의 지능제어)

  • Kim, Sung-Soo;Lee, Jae-Gi;Choi, Jin-Young
    • Journal of Institute of Control, Robotics and Systems
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    • v.6 no.2
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    • pp.127-137
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    • 2000
  • This paper presents a novel neural based controller which controls the water level of the nuclear power plant steam generator. The controller consists of a model reference feedback linearization controller and a PI controller for stabilizing the feedback linearization controller. The feedback linearization controller consists of a neural network model and an inversing module which uses the neural network model for computing the control input to the steam generator. We chose Piecewise Linearly Trained Network(PLTN) and Recurrent Neural Netwrok(RNN) for an approximator of the plant and used these approximators in calculating the input from the feedback linearization controller. Combining the above two controllers gives a result of better performance than the case which uses only a PI controller Each control result of PLTN and RNN is given.

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A Model of the Operator Cognitive Behaviors During the Steam Generator Tube Rupture Accident at a Nuclear Power Plant

  • Mun, J.H.;Kang, C.S.
    • Nuclear Engineering and Technology
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    • v.28 no.5
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    • pp.467-481
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    • 1996
  • An integrated framework of modeling the human operator cognitive behavior during nuclear power plant accident scenarios is presented. It incorporates both plant and operator models. The basic structure of the operator model is similar to that of existing cognitive models, however, this model differs from those existing ones largely in too aspects. First, using frame and membership function, the pattern matching behavior, which is identified as the dominant cognitive process of operators responding to an accident sequence, is explicitly implemented in this model. Second, the non-task-related human cognitive activities like effect of stress and cognitive biases such as confirmation bias and availability bias, are also considered. A computer code, OPEC is assembled to simulate this framework and is actually applied to an SGTR sequence, and the resultant simulated behaviors of operator are obtained.

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Modeling of Nuclear Power Plant S/G Downcomer Level using GA and Levenberg-Marquardt Algorithm (유전자 알고리즘과 Levenberg-Marquardt 알고리즘을 이용한 원전 증기발생기 수위 거동 모텔링)

  • Park, Chang-Hwan;Lee, Sang-Kyung;Lee, Un-Chul
    • Proceedings of the KIEE Conference
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    • 2001.11c
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    • pp.204-208
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    • 2001
  • In this paper, we induce the linear transfer function of Downcomer water level of NPP(Nuclear Power Plant) Steam Generator using Genetic Algorithm and Levenberg-Marquardt Algorithm. The characteristic of NPP S/G mechanism is so high-non-linear that it is hard to achieve mathematical expression. So we use non-mathematical Algorithms to get the model function of NPP S/G water level. S/G level controller would be designed with this transfer function as the plant.

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Robust Stability Analysis of STATCOM System for Power Quality Enhancement (전력 품질 개선을 위한 STATCOM 시스템의 강인 안정도 해석)

  • Sung, Hwa-Chang;Park, Jin-Bae;Tak, Myung-Hwan;Joo, Young-Hoon
    • Journal of the Korean Institute of Intelligent Systems
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    • v.20 no.2
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    • pp.220-225
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    • 2010
  • This paper deals with the robust stability analysis of STATCOM (Static Synchronous Compensator) power system for power quality enhancement and power system stability. The STATCOM plays an important role in controlling the reactive power flow to the power network and hence the system voltage fluctuations and stability. The control areas of this plant are very large and the overall composition of the system is nonlinear. Also, STATCOM is influence of the uncertainties so that it is necessary to apply the new control technique. For solving these problems, we perform the fuzzy modeling and robust analysis for STATCOM system.

Analysis on the Energy Balance and Performance Variation of the Power Plant by using the Heavy Residual Oil (중질잔사유 적용시 발전플랜트의 에너지 수지 및 성능 변화 분석)

  • Park, Ho-Young;Kim, Tae-Hyung
    • Journal of Energy Engineering
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    • v.17 no.2
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    • pp.107-115
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    • 2008
  • The numerical analysis of energy and material balance, and plant performance has been carried out when applying the heavy residual oil instead of heavy oil to the existing heavy oil power station. The performance analysis model has been constructed for A heavy oil power station in Korea, and the modeling results were compared with the design data in order to ensure the validity of the model, and further compared with the plant operation data. With the heavy residual oil, the simulation gave 315 MW in power output, which is higher than that of the heavy oil combustion, but the plant efficiency turned out to be lower. The sensitivity analysis of heat rate for the changes in cooling water and ambient temperature, flue gas recirculation and power output has provided valuable information for the optimal operation of the power station.

A Study on the Design of Database to Improve the Capability of Managing Offshore Wind Power Plant (해상풍력 풍력시스템의 관리능력 향상을 위한 데이터베이스 설계에 관한 연구)

  • Kim, Do-Hyung;Kim, Chang-Suk;Kyong, Nam-Ho
    • Journal of the Korean Solar Energy Society
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    • v.30 no.3
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    • pp.65-70
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    • 2010
  • As for the present wind power industry, most of the computerization for monitoring and control is based on the traditional development methodology, but it is necessary to improve SCADA system since it has a phenomenon of backlog accumulation in the applicable aspect of back-data as well as in the operational aspect in the future. Especially for a system like offshore wind power where a superintendent cannot reside, it is desirable to operate a remote control system. Therefore, it is essential to establish a monitoring system with appropriate control and monitoring inevitably premised on the integrity and independence of data. As a result, a study was carried out on the modeling of offshore wind power data-centered database. In this paper, a logical data modeling method was proposed and designed to establish the database of offshore wind power. In order for designing the logical data modeling of an offshore wind power system, this study carried out an analysis of design elements for the database of offshore wind power and described considerations and problems as well. Through a comparative analysis of the final database of the newly-designed off-shore wind power system against the existing SCADA System, this study proposed a new direction to bring about progress toward a smart wind power system, showing a possibility of a service-oriented smart wind power system, such as future prediction, hindrance-cause examination and fault analyses, through the database integrating various control signals, geographical information and data about surrounding environments.

Performances of the Directional Control Solenoid Valve for a Combined Power Plant

  • Kim, Chul-Jin;Yun, Yu-Seong;Kim, Do-Tae;Lee, Il-Young
    • International Journal of Safety
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    • v.11 no.2
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    • pp.10-14
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    • 2012
  • Recently, the combined power plants are refocused rapidly as a replaceable energy system of the nuclear power plant. The large turbine is revolved highly at 1800~3600 rpm. Thus, the turbine speed should be monitored with mechanical and electrical method for a safety. The electrical cutoff valve which blocks the flow channel with the electrical signal is with a built in. The aim of this study is to develop a manufacturing technology through by the localization of a solenoid actuated directional control valve. Especially the results show performances of the solenoid valve by the experiments and modeling and the reliability estimation. Applied load port pressure was changed rapidly on the form of a quadratic curve over time. And in the cases of square waveform when 0~100 V and 20~120 V input voltage, it was driven on a stable state until 13.4 Hz and 16.6 Hz, respectively. We think that this study will give useful data for the electricity safety system of the combined power plant gas turbine.

Development and Application of Detailed Procedure to Evaluate Fatigue Integrity for Major Components Considering Operating Conditions in the Nuclear Power Plant (원전 운전환경을 고려한 주기기 피로 건전성 상세평가 절차개발 및 적용)

  • Kim, Byong-Sup;Kim, Tae-Soon
    • Journal of the Korean Society of Safety
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    • v.21 no.6 s.78
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    • pp.20-25
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    • 2006
  • In the design of class 1 components to apply ASME code section III NB, a fatigue is considered as one of the important failure mechanisms. Fatigue analysis procedure and standard fatigue design curve(S-N curve) is suggested in ASME code, which had to be performed to meet the integrity of components at the design step. As the plant life extension for operating power plants and the long-lived plant design, however, are being progressed, the fact which the existing ASME fatigue design curve can not consider fatigue effects sufficiently comes to the fore. To find the technical solution for these problems, a number of researches and discussion are continued up to now. In this study, the detailed fatigue analyses using the 3 dimensional modeling for the fatigue-weakened components were performed to develop the optimized fatigue analysis procedure and their results are compared with other reference solutions.

Evaluation of Corrosion Protection Efficiency and Analysis of Damage Detectability in Buried Pipes of a Nuclear Power Plant with 3D FEM (3D FEM 모델링을 이용한 원전 매설배관의 방식성능 평가 및 결함탐지능 분석)

  • Chang, Hyun Young;Park, Heung Bae;Kim, Ki Tae;Kim, Young Sik;Jang, Yoon Young
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.11 no.2
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    • pp.61-67
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    • 2015
  • 3D FEM modeling based on 3D CAD data has been performed to evaluate the efficiency of CP system in a real operating nuclear power plant. The results of it successfully produced sophisticated profiles of electrolytic potential and current distributions in the soil of an interested area. This technology is expected to be a breakthrough for detection technology of damages on buried pipes when it comes into combining with a brand of area potential earth current (APEC) and ground penetrated radar (GPR) technologies. 2D current distribution and 2D current vectors on the earth surface from the APEC survey will be used as boundary conditions with exact 3D geometry data resulting in visualization of locations and extents of corrosion damages on the buried pipes in nuclear power plants.

Numerical study to reproduce a real cable tray fire event in a nuclear power plant

  • Jaiho Lee ;Byeongjun Kim;Yong Hun Jung;Sangkyu Lee;Weon Gyu Shin
    • Nuclear Engineering and Technology
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    • v.55 no.4
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    • pp.1571-1584
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    • 2023
  • In this study, a numerical analysis was performed as part of an international joint research project to reproduce a real cable tray fire that occurred in the heater bay area of the turbine building of a nuclear power plant. A sensitivity analysis was performed on various input parameters to derive results consistent with the sprinkler activation time obtained from the fire event analysis. For all sensitive parameters, the normalized sprinkler activation time correlated well with the power function of the normalized sprinkler height. A correlation equation was developed to identify the sprinkler activation time at any location when determining the slope or fire growth rate under the conditions assuming a linear or t-squared heat release rate (HRR) time curve. Various cable fire growth assumptions were used to determine which assumption was better to provide the prediction coincident with the information given from the fire event analysis in terms of the sprinkler activation time and total energy generated from cables damaged by fire. In the comprehensive analysis of all the sensitive parameters, the standard deviation of the input parameters increased as the sprinkler height decreased. Within the range of the sensitivity parameter values given in this study, when considering all sprinkler heights, the standard deviation of the cable model change was the largest and that of the overhang position change was the smallest.