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Iwamoto, Osamu
Journal of nuclear science and technology, 01/2007, Volume: 44, Issue: 5Journal Article
A new comprehensive code for nuclear data evaluation, CCONE, has been developed for the evaluation of nuclear data for actinides. Neutron-induced reaction cross sections for uranium isotopes (A = 232, 233, 234, 235, 236, 237, 238) were analyzed for incident energies from 10 keV to 20 MeV using CCONE in order to validate its capability. Reproducibility of the cross section calculations for various reactions such as total, fission, capture, and (n, 2n) was tested using simple parameterization. The calculated cross sections and neutron emission spectra show good agreement with the experimental data.
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