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Development concept for a small, split-core, heat-pipe-cooled nuclear reactorThere have been two main deterrents to the development of semiportable nuclear reactors. One is the high development costs; the other is the inability to satisfy with assurance the questions of operational safety. This report shows how a split-core, heat-pipe cooled reactor could conceptually eliminate these deterrents, and examines and summarizes recent work on split-core, heat-pipe reactors. A concept for a small reactor that could be developed at a comparatively low cost is presented. The concept would extend the technology of subcritical radioisotope thermoelectric generators using 238 PuO2 to the evolution of critical space power reactors using 239 PuO2.
Document ID
19740012125
Acquisition Source
Legacy CDMS
Document Type
Technical Memorandum (TM)
Authors
Lantz, E. (NASA Lewis Research Center Cleveland, OH, United States)
Breitwieser, R. (NASA Lewis Research Center Cleveland, OH, United States)
Niederauer, G. F. (NASA Lewis Research Center Cleveland, OH, United States)
Date Acquired
September 3, 2013
Publication Date
April 1, 1974
Subject Category
Nuclear Engineering
Report/Patent Number
NASA-TM-X-2996
E-7542
Accession Number
74N20238
Funding Number(s)
PROJECT: RTOP 503-25
Distribution Limits
Public
Copyright
Work of the US Gov. Public Use Permitted.

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