Method for generating neutronic data bases for transient reactor calculations [electronic resource]
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| Online Access: |
Online Access |
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| Corporate Authors: | , |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Aiken, S.C. : Oak Ridge, Tenn. :
United States. Dept. of Energy. Savannah River Site ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1976.
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| Subjects: |
| Abstract: | A method has been devised for the generation of neutronic data bases for use in reactor transient calculations using diffusion theory. The method makes use of scientific knowledge and experience in the trial and error approach to the correlation process. The data requirements for the support of the data base are made practical by the use of the multi-regime concept and the application of the Box-Behnken or other incomplete factorial design concepts. The method has been thoroughly tested and has been found to produce adequate representations of the fewgroup cross sections for detailed transient analysis studies with multidimensional reactor code systems. |
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| Item Description: | Published through SciTech Connect. 01/01/1976. "dp-ms-76-71" " conf-770304-1" Analysis of nuclear systems, Tucson, AZ, USA, 28 Mar 1977. Parks, P.B.; Buckner, M.R. |
| Physical Description: | Pages: 35 : digital, PDF file. |