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
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