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Calculated cross sections for neutron induced reactions on sup 19 F and uncertainties of parameters [electronic resource].

Published
Washington, D.C : United States. Dept. of Energy. Office of Energy Research, 1990.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: (73 pages) : digital, PDF file
Additional Creators
Oak Ridge National Laboratory, United States. Department of Energy. Office of Energy Research, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
Nuclear model codes were used to calculate cross sections for neutron-induced reactions on ¹⁹F for incident energies from 2 to 20 MeV. The model parameters in the codes were adjusted to best reproduce experimental data and are given in this report. The calculated results are compared to measured data and the evaluated values of ENDF/B-V. The covariance matrix for several of the most sensitive model parameters is given based on the scatter of measured data around the theoretical curves and the long-range correlation error of measured data. The results of these calculations form the basis for the new ENDF/B-VI fluorine evaluation. 44 refs., 64 figs., 14 tabs.
Report Numbers
E 1.99:ornl/tm-11672
ornl/tm-11672
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
09/01/1990.
"ornl/tm-11672"
"DE91005603"
Larson, D.C.; Fu, C.Y.; Zhao, Z.X. . Inst. of Atomic Energy.
Funding Information
AC05-84OR21400
View MARC record | catkey: 13842563