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Preliminary neutronic analysis of a cavity test reactorA reference configuration was calculated for a cavity test reactor to be used for testing the gascore nuclear rocket concept. A thermal flux of 4.1 x 10 to the 14th power neutrons per square centimeter per second in the cavity was provided by a driver fuel loading of 6.4 kg of enriched uranium in MTR fuel elements. The reactor was moderated and cooled by heavy water and reflected with 25.4 cm of beryllium. Power generation of 41.3 MW in the driver fuel is rejected to a heat sink. Design effort was directed toward minimization of driver power while maintaining 2.7 MW in the cavity during a test run. Ancillary data on material reactivity worths, reactivity coefficients, flux spectra, and power distributions are reported.
Document ID
19730009949
Document Type
Technical Memorandum (TM)
Authors
Whitmarsh, C. L., Jr.
(NASA Lewis Research Center Cleveland, OH, United States)
Date Acquired
September 2, 2013
Publication Date
March 1, 1973
Subject Category
Nuclear Engineering
Report/Patent Number
NASA-TM-X-2743
E-7193
Funding Number(s)
PROJECT: RTOP 503-04
Distribution Limits
Public
Copyright
Work of the US Gov. Public Use Permitted.

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