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
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