• DocumentCode
    1170609
  • Title

    Hallam Nuclear Power Facility Prototype for Advanced Sodium-Cooled Power Stations

  • Author

    Dickinson, R.W. ; Gerber, R.C. ; Larson, C.L.

  • Volume
    80
  • Issue
    3
  • fYear
    1961
  • fDate
    4/1/1961 12:00:00 AM
  • Firstpage
    1008
  • Lastpage
    1011
  • Abstract
    The sodium-cooled graphitemoderated nuclear reactor concept is described. The Hallam Nuclear Power Facility (HNPF) for producing superheated steam to generate 75 electrical megawatts (mwe) net power represents a significant step toward the ultimate capabilities of this concept. A larger plant design, capable of 360-mwe gross output, is also presented. The advanced design is expected to produce steam thermodynamically comparable to modern steam plants economically competitive with fossil fueled stations in many areas of the United States. Two important characteristics of the sodium-cooled reactor concept are the excellent heat ransfer properties of liquid sodium and the inherent safety of a low-pressure reactor system. These characteristics are utilized extensively in this concept to minimize total power cost.
  • Keywords
    Costs; Fission reactors; Fuel economy; Inductors; Nuclear power generation; Power generation; Power generation economics; Power system economics; Prototypes; Safety;
  • 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.1961.4501197
  • Filename
    4501197