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Evaluated delayed neutron spectra and their importance in reactor calculations

Journal Article · · Nucl. Sci. Eng.; (United States)
OSTI ID:7086346
Delayed neutron emission spectra from thermal-neutron fission of /sup 233/U, /sup 235/U, /sup 239/Pu, and /sup 241/Pu, from fast-neutron fission of /sup 232/Th, /sup 235/U, /sup 238/U, and /sup 239/Pu and from high-energy neutron (14.7-MeV) fission of /sup 235/U and /sup 238/U, for six groups of delayed neutrons are evaluated. The evaluation is based on recent measurements of delayed neutron spectra from 20 fission product isotopes. The data are presented in graphic form and are compared to directly measured equilibrium spectra whenever available. Tables with a convenient 54-energy-group structure are provided to facilitate their use in reactor calculations. The results of a limited number of two-dimensional, multigroup, transient calculations for the Clinch River Breeder Reactor core, using the newly evaluated spectra, are compared with calculations using some older spectra. The importance of the inclusion of these data in reactor dynamic calculations is evaluated. 34 figures, 13 tables. 37 references.
OSTI ID:
7086346
Journal Information:
Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 62:4; ISSN NSENA
Country of Publication:
United States
Language:
English