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Measurement and calculation of average activation cross sections in the spontaneous fission neutron field of /sup 252/Cf

Journal Article · · Nucl. Sci. Eng.; (United States)
OSTI ID:6237485
The measuring procedure for the determination of neutron activation cross sections averaged over the neutron spectrum of /sup 252/Cf is described. Measurements were done in a low-scattering irradiation facility that provides a nearly undisturbed field of neutrons emitted with the spontaneous fission of /sup 252/Cf. The following neutron reactions were investigated: /sup 113/In(n,n..gamma..), /sup 115/In(n,n'), /sup 115/In(n,n'), /sup 197/Au(n,..gamma..), and /sup 197/Au(n,2n). The resulting average cross sections were compared with those of other experiments. In addition, calculations of average cross sections were performed. The results of the present and of earlier measurements were summarized and compared with calculated average cross sections obtained by folding the spectral distribution of /sup 252/Cf neutrons with different sigma(E) data (ENDF/B-IV, ENDF/B-V, and recent experiments). 1 figure, 3 tables.
Research Organization:
Physikalische-Technische Bundesanstalt, Braunschweig, Germany
OSTI ID:
6237485
Journal Information:
Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 69:2; ISSN NSENA
Country of Publication:
United States
Language:
English

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