• DocumentCode
    1171857
  • Title

    Statatus of the High-Temperature Gas-Cooled Reactor

  • Author

    LeClair, T.G.

  • Volume
    81
  • Issue
    3
  • fYear
    1962
  • fDate
    4/1/1962 12:00:00 AM
  • Firstpage
    371
  • Lastpage
    375
  • Abstract
    General Atomic´s High-Temperature Gas-Cooled Reactor (HTGR) is discussed, with special reference to the 40-Mwe (electrical megawatts) prototype HTGR plant to be built at Peach Bottom, Pa. This plant will supply steam at 1,000 F (degrees Fahrenheit) and 1450 psia (pounds per square inch absolute); will have a fuel burn-up of 50,000 mw-davs per tonne; and will operate for 3 years without refueling, Recent developments in the prototype HTGR prograni include coated fuel particles, the single-wall fuel element, and measurements of the Doppler coefficient, using the HTGR critical assembly.
  • Keywords
    Acceleration; Damping; Delay effects; Equations; Inductors; Power system interconnection; Relays; Testing; Turbines; Velocity measurement;
  • fLanguage
    English
  • Journal_Title
    Power Apparatus and Systems, Part III. Transactions of the American Institute of Electrical Engineers
  • Publisher
    ieee
  • ISSN
    0097-2460
  • Type

    jour

  • DOI
    10.1109/AIEEPAS.1962.4501335
  • Filename
    4501335