• DocumentCode
    1532355
  • Title

    A constant reactor-outlet-temperature control system for nuclear power plants

  • Author

    Stubbs, Gilbert S.

  • Author_Institution
    The Franklin Institute Laboratories for Research and Development Philadelphia, Pennsylvania
  • Issue
    1
  • fYear
    1954
  • Firstpage
    8
  • Lastpage
    11
  • Abstract
    Most nuclear power plant designs involve the transmission of heat from the core of a nuclear reactor to the boiler of a steam plant by a gas or liquid coolant. A primary function of the power plant control system is to control the temperature of this coolant to provide the desired heat transfer rates and temperature levels in the boiler and reactor. The control system must also prevent transient excusions in the coolant temperature from exceeding the material and structural limitations of the power plant. Major obstacles to the control of transient excursions in coolant temperature are (1) the tendency of these temperature variations to be recirculated in the closed coolant loop, (2) the long transport lags associated with the coolant circulation, and (3) the large inherent time lags of thermometers measuring the coolant temperature.
  • Keywords
    Boilers; Coolants; FIssion reactors; Inductors; Nuclear power generation; Temperature measurement;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, Transactions of the Institute of Radio Engineers Professional Group on
  • Publisher
    ieee
  • ISSN
    0277-6278
  • Type

    jour

  • DOI
    10.1109/IREPGTNS.1954.6499134
  • Filename
    6499134