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Technology of nuclear-Brayton space power systemsThe 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. Systems 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
19720004332
Acquisition Source
Legacy CDMS
Document Type
Conference Paper
Authors
English, R. E. (NASA Lewis Research Center Cleveland, OH, United States)
Date Acquired
September 2, 2013
Publication Date
January 1, 1971
Subject Category
Auxiliary Systems
Report/Patent Number
NASA-TM-X-67957
Report Number: NASA-TM-X-67957
Meeting Information
Meeting: 1971 Am. Nucl. Soc. Meeting
Location: Miami, FL
Country: United States
Start Date: October 17, 1971
End Date: October 21, 1971
Accession Number
72N11981
Distribution Limits
Public
Copyright
Work of the US Gov. Public Use Permitted.

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