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Dynamics of heat-pipe reactorsA split-core heat pipe reactor, fueled with either U(233)C or U(235)C in a tungsten cermet and cooled by 7-Li-W heat pipes, was examined for the effects of the heat pipes on reactor while trying to safely absorb large reactivity inputs through inherent shutdown mechanisms. Limits on ramp reactivity inputs due to fuel melting temperature and heat pipe wall heat flux were mapped for the reactor in both startup and at-power operating modes.
Document ID
19720004950
Acquisition Source
Legacy CDMS
Document Type
Technical Memorandum (TM)
Authors
Niederauer, G. F.
(NASA Lewis Research Center Cleveland, OH, United States)
Date Acquired
September 2, 2013
Publication Date
January 1, 1971
Subject Category
Nuclear Engineering
Report/Patent Number
NASA-TM-X-67966
E-6678
Report Number: NASA-TM-X-67966
Report Number: E-6678
Meeting Information
Meeting: Winter Meeting of the Am. Nucl. Soc.
Location: Miami
Start Date: October 17, 1971
End Date: October 21, 1971
Accession Number
72N12599
Distribution Limits
Public
Copyright
Work of the US Gov. Public Use Permitted.
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