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Evaluation of 235U Neutron Cross Section and Gamma Ray Production Data for ENDF

Evaluation of 235U Neutron Cross Section and Gamma Ray Production Data for ENDF
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Release: 1980
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A discussion is given of the evaluation of neutron and gamma ray production cross sections of 235U from 10−5 eV to 20 MeV and the parts contributed by the author. All available new data are included in this evaluation, and the procedures adopted to assess the experimental data and adopt a set of recommended values are described. 22 figures, 10 tables.