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


Book Description

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.




Evaluation of Natural Chromium Neutron Cross Sections for ENDF


Book Description

This report describes the evaluation of natural chromium for ENDF/B-V. Neutron cross sections and photon production are presented for the energy range 10−5 eV to 20 MeV. An extreme effort was made to incorporate all available new experimental data since the previous ENDF/B-IV evaluation. Particular consideration was also given to consistency between calculation and experimental data and are described in detail. Covariance files are given and are based on model code uncertainties along with empirical data.










Calculation of Neutron and Gamma-ray Production Cross Sections for Calcium from 8 to 20 MeV.


Book Description

Nuclear model calculations used for the previous evaluation for calcium (ENDF/B-V MAT 1320) lacked the effects of precompound particle emission. Experimental information now available suggests that these effects are significant from 8 to 20 MeV. Results of new calculations made to include such effects in all reaction cross sections from 8 to 20 MeV are presented. The resulting data set was prepared in the ENDF/B-V format and is referred to as Material 4152 Modification V in the DNA cross-section library.