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Analysis of a boron-carbide-drum-controlled critical reactor experimentIn order to validate methods and cross sections used in the neutronic design of compact fast-spectrum reactors for generating electric power in space, an analysis of a boron-carbide-drum-controlled critical reactor was made. For this reactor the transport analysis gave generally satisfactory results. The calculated multiplication factor for the most detailed calculation was only 0.7-percent Delta k too high. Calculated reactivity worth of the control drums was $11.61 compared to measurements of $11.58 by the inverse kinetics methods and $11.98 by the inverse counting method. Calculated radial and axial power distributions were in good agreement with experiment.
Document ID
19730003974
Acquisition Source
Legacy CDMS
Document Type
Technical Memorandum (TM)
Authors
Mayo, W. T.
(NASA Lewis Research Center Cleveland, OH, United States)
Date Acquired
September 2, 2013
Publication Date
November 1, 1972
Subject Category
Nuclear Engineering
Report/Patent Number
NASA-TM-X-2680
E-7071
Report Number: NASA-TM-X-2680
Report Number: E-7071
Accession Number
73N12701
Funding Number(s)
PROJECT: RTOP 503-25
Distribution Limits
Public
Copyright
Work of the US Gov. Public Use Permitted.
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