R-Matrix Analysis of Neutron Effective Total Cross Section, Fission Cross Section and Capture Cross Section of 233U in the Energy Range from Thermal to 150eV.

Abstract

The Reich-Moore approximation of the R-matrix theory was applied to the analysis of selected measurements of neutron effective total cross sections, fission cross sections and capture cross sections of 233U in the energy range from thermal to 150 eV. The resonance parameters were obtained by fitting the experimental data by the Bayesian code SAMMY. Results of the calculated cross sections are compared with the corresponding experimental data in graphs and tables. The statistical properties of the resonance parameters were examined and the average parameters were obtained. The resonance parameters are given in an ENDF-6 format file available from the JAER1 Nuclear Data Center and from the NEA Data Bank (OECD, Paris).