330-MW(e) Fort St. Vrain high-temperature gas-cooled reactor

Description of the principal design features of the 330 MW(e) Fort Saint Vrain high-temperature gas-cooled reactor system. The reactor will utilize the same fundamental principles as are incorporated in the 40 MW(e) prototype HTGR located at Peach Bottom, Pa. These principles include the use of heli...

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Bibliographic Details
Published in:Nuclear engineering and design 1968-01, Vol.7 (4), p.312-321
Main Authors: Habush, A.L., Harris, A.M.
Format: Article
Language:English
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Summary:Description of the principal design features of the 330 MW(e) Fort Saint Vrain high-temperature gas-cooled reactor system. The reactor will utilize the same fundamental principles as are incorporated in the 40 MW(e) prototype HTGR located at Peach Bottom, Pa. These principles include the use of helium gas as the coolant, graphite as the fuel-element structural material, moderator, and reflector, and a uranium-thorium fuel cycle. The primary coolant system will incorporate, however, a number of significant new design features, the most prominent of which are the use of a prestressed concrete reactor vessel (PCRV), once-through modular steam generators, steam-driven axial-flow helium circulators, and hexagonal-shaped graphite fuel elements incorporating improved carbon-coated particles.
ISSN:0029-5493
1872-759X
DOI:10.1016/0029-5493(68)90064-2