R Matrix Analysis of the ²⁴¹ Pu Neutron Cross Sections in the Thermal to 300-eV Energy Range

A description is given of the analysis of the ²⁴¹Pu neutron cross sections in the resolved resonance region at Oak Ridge National Laboratory using the multilevel, multichannel Reich-Moore code SAMMY. The resonance parameters were obtained in the 0- to 300-eV energy range. The statistical properties of the parameters are discussed. Tabulated and graphical comparisons between the experimental data and the calculated cross sections are given. The results are available in ENDF/B-V format and are proposed for the evaluated data libraries ENDF/B-VI and JEF2.