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Technology of nuclear-Brayton space power systems.The present technology of Brayton power systems is reviewed. The potential for even higher system efficiency at the 10 kWe level is assessed as well as the potential for comparable efficiency with an output of 1 or 2 kWe. System accommodation of isotope decay is briefly discussed. The salient features are described for a Brayton power system based on this technology and employing the ZrH reactor. Reactor lives for this and competitive systems are compared. Growth capability with an advanced reactor is assessed. A concept for application of this technology to driving a gas-dynamic laser is described.
Document ID
19720030757
Acquisition Source
Legacy CDMS
Document Type
Conference Paper
Authors
English, R. E. (NASA Lewis Research Center Cleveland, Ohio, United States)
Date Acquired
August 6, 2013
Publication Date
October 1, 1971
Subject Category
Nuclear Engineering
Meeting Information
Meeting: American Nuclear Society, Winter Meeting
Location: Miami Beach, FL
Start Date: October 17, 1971
End Date: October 21, 1971
Sponsors: American Nuclear Society
Accession Number
72A14423
Distribution Limits
Public
Copyright
Other

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