• Title/Summary/Keyword: Steam Power Plant

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Thermodynamic model of one of the super heaters and the related spray in the Nekka power plant and Presenting SCO method to control boiler temperature

  • Zalloi, Mehdi;Barghandan, Saeed;Badamchizadeh, M.A.
    • 제어로봇시스템학회:학술대회논문집
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    • 2005.06a
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    • pp.129-133
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    • 2005
  • In this paper, first the thermodynamic model is presented to one of the super heaters and sprays of the Nekka power plant and then its unknown parameters are identified according to the registered data of the power plant. SCO control method is introduced to control the external steam temperature of super heater. Finally the conventional method in power plant for controlling external steam temperature of super heater is compared with new method and their performances are presented..

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The improvement method for power plant boiler temperature nonuniformity of heat transfer tube bank flow path (발전용 보일러 전열 튜브 유로내 온도분포 불균일 개선기법)

  • Jung, Hoon;Kim, Bum-Shin;Jang, Suck-Won;Ahn, Yeon-Shik;Park, Gun-Bok;Whang, Jung-Ho
    • Proceedings of the KSME Conference
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    • 2001.11b
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    • pp.837-841
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    • 2001
  • Almost all power plant boiler has temperature distribution nonuniformity problem in heat transfer tube flow path. It can cause hot spot damage of superheated or reheated heat transfer section and reduce maintenance schedule when nonuniformity is severe. There are two solutions for improvement temperature nonuniformity. one is change of gas flow distribution of gas path and the other is contorl steam flow in tube bank. Of course, first method is very difficulty to apply but second method is'nt. In this paper, control steam flow is used to solve temperature nonuniformity of power plant boiler.

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Immune Based 2-DOF PID Controller Design for Complex Process Control

  • Kim, Dong-Hwa
    • 제어로봇시스템학회:학술대회논문집
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    • 2002.10a
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    • pp.70.2-70
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    • 2002
  • In the thermal power plant, it is difficult to maintain strict control of the steam temperature in order to avoid thermal stress, because of variation of the heating value according to the fuel source, the time delay of changes in main steam temperature versus changes in fuel flow rate, difficulty of control on the main steam temperature control and the reheater steam temperature control system owing to the dynamic response characteristics of changes in steam temperature and the reheater steam temperature, fluctuation of inner fluid water and steam flow rates widely during load-following operation. Up to the present time, the PID controller has been used to operate this system...

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Power and Efficiency Optimization through Exergy Analysis of Power Plant (발전 플랜트의 엑서지 해석으로부터 발전량 및 발전효율 최적화)

  • Kim, Deok-Jin;Lee, Jae-Byoung;Kang, Su-Hwan
    • Plant Journal
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    • v.9 no.3
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    • pp.43-47
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    • 2013
  • Even if an expert who has majored energy engineering, it is a difficult concept to understand power output optimization and power efficiency optimization. In this study a diagram applying thermodynamic state value as specific exergy and exergy ratio was developed. Although general peoples who did not major energy engineering can be easily understand the concept of power output optimization and power efficiency through the developed diagram. A represented property that can identify the performance of power plant is the main steam temperature and pressure. At the developed diagram the maximum power output line and maximum power efficiency line are shown according to the temperature and pressure of main steam. Therefore we can identify how much a power plant approach to maximum power output and maximum power efficiency.

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Exergy and exergoeconomic analysis of hydrogen and power cogeneration using an HTR plant

  • Norouzi, Nima;Talebi, Saeed;Fani, Maryam;Khajehpour, Hossein
    • Nuclear Engineering and Technology
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    • v.53 no.8
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    • pp.2753-2760
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    • 2021
  • This paper proposes using sodium-cooled fast reactor technologies for use in hydrogen vapor methane (SMR) modification. Using three independent energy rings in the Russian BN-600 fast reactor, steam is generated in one of the steam-generating cycles with a pressure of 13.1 MPa and a temperature of 505 ℃. The reactor's second energy cycles can increase the gas-steam mixture's temperature to the required amount for efficient correction. The 620 ton/hr 540 ℃ steam generated in this cycle is sufficient to supply a high-temperature synthesis current source (700 ℃), which raises the steam-gas mixture's temperature in the reactor. The proposed technology provides a high rate of hydrogen production (approximately 144.5 ton/hr of standard H2), also up to 25% of the original natural gas, in line with existing SMR technology for preparing and heating steam and gas mixtures will be saved. Also, exergy analysis results show that the plant's efficiency reaches 78.5% using HTR heat for combined hydrogen and power generation.

A study on development of a vision system for the test of steam generator holes in nuclear power plants (원전 증기 발생기 세관 검사용 비젼시스템 개발에 관한 연구)

  • 왕한홍;김종수;한성현;심상한
    • 제어로봇시스템학회:학술대회논문집
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    • 1996.10b
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    • pp.101-104
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    • 1996
  • In nuclear power plants, workers are reluctant of works in steam generator because of the high radiation environment and limited working space. It is strongly recommended that the examination and maintenance works be done by an automatic system for the protection of the operator from the radiation exposure. In this paper, it is proposed a new approach to the development of the automatic vision system to examine and repair the steam generator tubes at remote distance. Digital signal processors are used in implementing real time recognition and examination of steam generator holes in the proposed vision system. Performance of proposed digital vision system is illustrated by experiment for similar steam generator model.

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A Study on Vision System Design for Automatic Inspection of Steam Generator in Nuclear Power Plants (원전 스팀 제너레이터 세관 자동검사용 비젼시스템 설계에 관한 연구)

  • 한성현;서운학;천영신;이만형
    • Journal of Institute of Control, Robotics and Systems
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    • v.4 no.5
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    • pp.658-665
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    • 1998
  • In this paper, we propose a new approach to the development of the automatic vision system to examine and repair the steam generator tubes at remote distance. In nuclear power plants, workers are reluctant of works in steam generator because of the high radiation environment and limited working space. It is strongly recommended that the examination and maintenance works be done by an automatic system for the protection of the operator from the radiation exposure. Digital signal processors are used in implementing real time recognition and examination of steam generator tubes in the proposed vision system. Performance of the proposed digital vision system is illustrated by simulation and experiment for similar steam generator model.

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Development of Automatic Inspection and Maintenance Technology for Steam Generator in Nuclear Power Plants (원자력 발전소 증기세관 자동검사 및 보수 기술개발)

  • Seo, W.H.;Jung, D.Y.;Lee, J.W.;Han, S.H.
    • Proceedings of the KSME Conference
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    • 2000.04a
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    • pp.542-547
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    • 2000
  • In this paper, we propose a new approach to the development of the automatic vision system to examine and repair the steam generator tubes at remote distance. In nuclear power plants, workers are reluctant of works in steam generator because of the high radiation environment and limited working space. It is strongly recommended that the examination and maintenance works be done by an automatic system for the protection of the operator from the radiation exposure. Digital signal processors are used in implementing real time recognition and examination of steam generator tubes in the proposed vision system. Performance of proposed digital vision system is illustrated by simulation and experiment for similar steam generator model.

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A Study on Vision System Design for Automatic Inspection of Steam Generator in Nuclear Power Plants (원전 스팀제너레이터 세관 자동검사용 로봇 비젼시스템 설계에 관한 연구)

  • 서운학
    • Proceedings of the Korean Society of Machine Tool Engineers Conference
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    • 1999.10a
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    • pp.571-578
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    • 1999
  • In this paper, we propose a new approach to the development of the automatic vision system to examine and repair the steam generator tubes at remote distance. In nuclear power plants, workers are reluctant of works in steam generator because of the high radiation environment and limited working space. It is strongly recommended that the examination and maintenance works be done by an automatic system for the protection of the operator from the radiation exposure. Digital signal processors are used in implementing real time recognition and examination of steam generator tubes in the proposed vision system. Performance of proposed digital vision system is illustrated by simulation and experiment for similar steam generator model.

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Open Die Forging of the Large Steel Forgings for Steam Generator (증기발생기용 대형 단강품의 자유단조)

  • 김동권;김재철;김영득;김동영
    • Proceedings of the Korean Society for Technology of Plasticity Conference
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    • 2003.10a
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    • pp.39-42
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    • 2003
  • Steam Generator has been manufactured by welding process after partial manufacturing of various steel forgings such as shell, head and tube sheet. Usually, these steel forgings are made by open die forging process. After steel melting and ingot making, open die forging has been carried out to get a good quality which means high soundness and homogeniety of the steel forgings by using high capacity hydraulic press. This paper introduced open die forging development status of the large steel forgings which is used for the steam generator of 1,400MW next generation nuclear power plant.

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