The Gas-Cooled Graphite-Moderated Reactor
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.
KeywordsPressure Vessel Fuel Element Fuel Assembly Steam Generator Boron Carbide
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- Central Electricity Generating Board (United Kingdom), Wylfa Power Station, available from CEGB, 825 Wimslow Road, Manchester, England.Google Scholar
- K. H. Dent, The Standing of Gas-Cooled Reactors, Nucl. Energy 19(4), 257–271 (1980).Google Scholar
- 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
- L. Massimo, The Physics of High Temperature Reactors, Pergamon Press, Oxford (1975).Google Scholar
- J. D. McKean, Hartlepool—A milestone in gas-cooled reactors, Nucl. Eng. Int. 14, 724–730 (1969).Google Scholar
- National Nuclear Corporation (United Kingdom), Heysham 2/Torness, Nucl. Eng. Int. 26(310), 27–42 (1981).Google Scholar
- R. E. Walker and T. A. Johnston, Fort Saint Vram nuclear power station, Nucl. Eng. Int. 14, 1064–1068 (1969).Google Scholar
- G. L. Wessman and T. R. Moffette, Safety design bases of the HTGR, Nucl. Saf. 14(6), 618–634 (1973).Google Scholar