• Title/Summary/Keyword: Advanced power system

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Practical Development and Evaluation of Advanced Alarm System for Nuclear Power Plant (원자력 플랜트의 개량형 경보시스템 개발 및 평가사례)

  • Jang Gui-Suk
    • Journal of KIISE:Computing Practices and Letters
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    • v.12 no.4
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    • pp.229-240
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    • 2006
  • The advanced Alarm System (AS) employs modem digital technology to implement the alarm functions of the NPP(Nuclear Power Plant). The use of modem digital technology can provide advanced alarm processing in which new algorithms such as a signal validation, advanced alarm processing logic and other features are applied to improve the control room man-machine interfaces. This paper will describe the design process of the AS of NPP, improving the system reliability and availability using the reliability prediction tool, design strategies regarding the human performance topics associated with a computer-based AS and the results of the performance analysis using a prototype of the AS.

A Matlab/Simulink-Based PV array-Supercapacitor Model Employing SimPowerSystem and Stateflow Tool Box

  • Hong, Won-Pyo
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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    • v.28 no.12
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    • pp.18-29
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    • 2014
  • This paper proposes the integration of photovoltaic (PV) and energy storage systems for sustained power generation. In this proposed system, whenever the PV system cannot completely meet load demands, the super capacitor provides power to meet the remaining load. A power management strategy is designed for the proposed system to manage power flows between PV array systems and supercapacitors (SC). The main task of this study was to design PV systems with storage strategies including MPPT with direct control and an advanced DC-link controller and to analyze dynamic model proposed for a PV-SC hybrid power generation system. In this paper, the simulation models for the hybrid energy system are developed using Matlab/Simulink, SimPowerSystems and Matlab/Stateflow tool. This is the key innovative contribution of the research paper. The system performances are verified by carrying out simulation studies using practical load demand profile and real weather data.

Tele-robotic Application for Nozzle Dam Maintenance Operation in Nuclear Power Plants

  • Seo, Yong-Chil;Kim, Chang-Hoi;Cho, Jae-Wan;Kim, Seung-Ho
    • 제어로봇시스템학회:학술대회논문집
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    • 2004.08a
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    • pp.1520-1524
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    • 2004
  • This paper describes the development of a robotic maintenance system for use in a maintenance operation of the nozzle dam in a water chamber of a steam generator at the Kori nuclear power plant in Korea. The robotic maintenance system was designed to minimize the personnel exposure to a hazardous radioactive environment. This robotic maintenance system is operated by a teleoperated control which was designed to perform the nozzle dam maintenance tasks in a remote manner without endangering the human workers. Specific maintenance tasks involve the transportation, insertion, and removal of nozzle dams in a water chamber inside a steam generator via a narrow man-way entrance port. The developed robotic maintenance system has two major subsystems: a two degrees of freedom guiding device acting as the main guiding arm and a master-slave manipulator with a kinematic dissimilarity. The mechanical design considerations, control system, and capabilities of the robotic maintenance system are presented. Finally, a graphical representation of the nozzle dam maintenance processes in a simulated work environment are also demonstrated.

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Design of power and phase feedback control system for ion cyclotron resonance heating in the Experimental Advanced Superconducting Tokamak

  • L.N. Liu;W.M. Zheng;X.J. Zhang;H. Yang;S. Yuan;Y.Z. Mao;W. Zhang;G.H. Zhu;L. Wang;C.M. Qin;Y.P. Zhao;Y. Cheng;K. Zhang
    • Nuclear Engineering and Technology
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    • v.56 no.1
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    • pp.216-221
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    • 2024
  • Ion cyclotron range of frequency (ICRF) heating system is an important auxiliary heating method in the experimental Advanced Superconducting Tokamak (EAST). In EAST, several megawatts of power are transmitted with coaxial transmission lines and coupled to the plasma. For the long pulse and high power operation of the ICRF waves heating system, it is very important to effectively control the power and initial phase of the ICRF signals. In this paper, a power and phase feedback control system is described based on field programmable gate array (FPGA) devices, which can realize complicated algorithms with the advantages of fast running and high reliability. The transmitted power and antenna phase are measured by a power and phase detector and digitized. The power and phase feedback control algorithms is designed to achieve the target power and antenna phase. The power feedback control system was tested on a dummy load and during plasma experiments. Test results confirm that the feedback control system can precisely control ICRF power and antenna phase and is robust during plasma variations.

The development of high fidelity Steam Generator three dimensional thermal hydraulic coupling code: STAF-CT

  • Zhao, Xiaohan;Wang, Mingjun;Wu, Ge;Zhang, Jing;Tian, Wenxi;Qiu, Suizheng;Su, G.H.
    • Nuclear Engineering and Technology
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    • v.53 no.3
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    • pp.763-775
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    • 2021
  • The thermal hydraulic performances of Steam Generator (SG) under both steady and transient operation conditions are of great importance for the safety and economy in nuclear power plants. In this paper, based on our self-developed SG thermal hydraulic analysis code STAF (Steam-generator Thermalhydraulic Analysis code based on Fluent), an improved new version STAF-CT (fully Coupling and Transient) is developed and introduced. Compared with original STAF, the new version code STAF-CT has two main functional improvements including "Transient" and "Fully Three Dimensional Coupling" features. In STAF-CT, a three dimensional energy transferring module is established which can achieve energy exchange computing function at the corresponding position between two sides of SG. The STAF-CT is validated against the international benchmark experiment data and the results show great agreement. Then the U-shaped SG in AP1000 nuclear power plant is modeled and simulated using STAF-CT. The results show that three dimensional flow fields in the primary side make significant effect on the energy source distribution between two sides. The development of code STAF-CT in this paper can provide an effective method for further SG high fidelity research in the nuclear reactor system.

Design of Economic Analysis Module for Waste Heat Recovery based on Systems Engineering Approach (시스템엔지니어링 기반 산업 폐열 발전시스템 경제성 분석 모듈 설계)

  • Kim, Joon Young;Cha, Jae Min;Park, Sung Ho;Shin, Jung Uk;Lee, Tae Kyong
    • Journal of the Korean Society of Systems Engineering
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    • v.14 no.1
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    • pp.1-12
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    • 2018
  • In the energy-guzzling industries such as steel making and cement, power plants utilizing waste heat have been attracting attention to increase energy efficiency. However, the existing economic analysis system doesn't consider the special working fluids and the cost models of the main equipment used in the waste heat recovery power plant. So it is difficult to estimate the plant economics accurately. Therefore, It is required to develop a economic analysis module that can more accurately evaluate for the power plant. In this study, the systems engineering approach was used to design and develop the module that systematically reflects the characteristics of the power plant and various requirements. Specifically, first, the special working fluids and main equipment applied to the power plant were investigated. Next, the cost models for each equipment were developed. Finally, the economic analysis module based on this was developed.

Code development and preliminary validation for lead-cooled fast reactor thermal-hydraulic transient behavior

  • Chenglong Wang;Chen Wang;Wenxi Tian;Guanghui Su;Suizheng Qiu
    • Nuclear Engineering and Technology
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    • v.56 no.6
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    • pp.2332-2342
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    • 2024
  • Lead-cooled fast reactors (LFRs) have a wide range of application scenarios, which require the thermal-hydraulic characteristics of LFRs to be reliable. In the present paper, the Lead-cooled fast reactor Thermal-Hydraulic Analysis Code LETHAC was developed, including the models of pipe, heat exchanger, and pool. To verify the correctness of LETHAC, two experimental facilities and three experimental cases were selected, including GFT and PLOFA tests for NACIE-UP and Test-1 for CIRCE. The calculated results show the same and consistent trend with the experimental data, but there are some discrepancies. It can be found that LETHAC is suitable and reliable in predicting the transient behavior of lead-cooled system.

Design and Analysis of a Power Control and Monitoring System for Buoy

  • Oh, Jin-Seok;Jo, Kwan-Jun
    • Journal of Advanced Marine Engineering and Technology
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    • v.33 no.7
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    • pp.1068-1074
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    • 2009
  • This paper describes a study for the buoy which should be operated by a stand-alone power system. The field of this study is related to a power system operated by two batteries which depends on the load power. The fluctuation of the voltages makes the life cycle of the battery shorten. The control algorithm has been proposed for reducing the voltage pulsation of the battery by operation strategy according to using purpose such as main or sub power supply system. The power system with battery is separated two parts and this has been proved through a simulation and a sea experiment. In order for the experiment to use a wireless monitoring system has been installed in buoy. This paper shows an excellent test result of wireless monitoring system for buoy.

A Study on Start·Stop System at Water Turbine-Generator for Tidal Power Plant (조력발전용 수차발전기의 기동·정지시스템에 관한 연구)

  • Oh, Min-Hwan;Park, Chul-Won
    • The Transactions of the Korean Institute of Electrical Engineers P
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    • v.63 no.2
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    • pp.113-118
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    • 2014
  • Tidal power is one of new and renewable energy sources. Tidal power is generated by using the gap in the water level between the water outside and inside the embankment. All tidal power plant in Korea were being operated by import of turn-key from abroad. The know-how and technology which are the most important to build predictive control system has become increasingly difficult to obtain from advanced countries because most of them avoid to transfer, which the domestic development of the control system is needed. In this paper, a study on start stop system at water turbine-generator for tidal power plant at the beginning of development was presented. For improvement the efficiency and develope of core technology of the start stop system, the technique and characteristics of tidal power, modeling, maximum generation calculation method, and optimal control of joint control system in Sihwa tidal power plant were studied.

Resonant Converter System for Control Power Supply (제어용 전원으로 사용가능한 공진형 컨버터 시스템)

  • Ji Jun-Keun;Lim Young-Ha
    • Proceedings of the KIPE Conference
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    • 2003.07a
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    • pp.69-72
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    • 2003
  • In this paper new control strategy of series resonant converter system for control power supply is suggested. Frequency controlled series resonant converter system is robust to load variations because it is POSR(parallel output series resonant) type. And it provides stable output voltage by changing switching frequency to input voltage variations. Firstly, operation analysis about suggested series resonant converter system was carried. Then simulations using ACSL(Advanced Continuous Simulation Language) and experiments to actual system were carried to prove characteristics of suggested system.

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