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Dynamics of heat-pipe reactors.A split-core heat-pipe reactor fueled with either 233-UC or 235-UC in a tungsten cermet and cooled by 7-Li-W heat pipes is examined for the effects of the heat pipes on this reactor in 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 are mapped for the reactor in both startup and at-power operating modes.
Document ID
19720030755
Acquisition Source
Legacy CDMS
Document Type
Conference Paper
Authors
Niederauer, G. F. (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
72A14421
Distribution Limits
Public
Copyright
Other

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