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The Gas-Cooled Graphite-Moderated Reactor

  • I. R. Cameron

Abstract

The graphite-moderated reactor has a longer history than any other type, since the first critical assembly constructed under the direction of Enrico Fermi at Chicago in December 1942 was a natural uranium, graphite- moderated reactor. The principal use of graphite-moderated reactors for power generation, however, has been in the United Kingdom and France. In both cases, the original motivation was the advantage of constructing a system combining natural uranium fuel with a readily available and relatively inexpensive moderator.

Keywords

Pressure Vessel Fuel Element Fuel Assembly Steam Generator Boron Carbide 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Bibliography

  1. Central Electricity Generating Board (United Kingdom), Wylfa Power Station, available from CEGB, 825 Wimslow Road, Manchester, England.Google Scholar
  2. K. H. Dent, The Standing of Gas-Cooled Reactors, Nucl. Energy 19(4), 257–271 (1980).Google Scholar
  3. English Electric, Babcock and Wilcox, Taylor Woodrow Atomic Power Construction Company Limited, Hinkley Point-Sizewell-Wylfa Head-A logical development, Nucl. Eng. (April 1965).Google Scholar
  4. L. Massimo, The Physics of High Temperature Reactors, Pergamon Press, Oxford (1975).Google Scholar
  5. J. D. McKean, Hartlepool—A milestone in gas-cooled reactors, Nucl. Eng. Int. 14, 724–730 (1969).Google Scholar
  6. National Nuclear Corporation (United Kingdom), Heysham 2/Torness, Nucl. Eng. Int. 26(310), 27–42 (1981).Google Scholar
  7. L. R. Shepherd, The future of the high temperature reactor, J. Br. Nucl. Energy Soc. 16(2), 123–132 (1977).MathSciNetGoogle Scholar
  8. R. E. Walker and T. A. Johnston, Fort Saint Vram nuclear power station, Nucl. Eng. Int. 14, 1064–1068 (1969).Google Scholar
  9. G. L. Wessman and T. R. Moffette, Safety design bases of the HTGR, Nucl. Saf. 14(6), 618–634 (1973).Google Scholar

Copyright information

© Plenum Press, New York 1982

Authors and Affiliations

  • I. R. Cameron
    • 1
  1. 1.University of New BrunswickSaint John, New BrunswickCanada

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