Description of evaluation of /sup nat/Pb performed for ENDF/B-VI

An evaluation of data for neutron induced reactions on natural lead was performed for ENDF/B-VI and is briefly reviewed. The evaluation is based on experimental data and results of model calculations which reproduce the experimental data. Evaluated data are given for neutron induced reaction cross sections, angular and energy distributions, and for gamma-ray production cross sections associated with the reactions. File 6 formats are used to represent energy-angle correlated data. Uncertainty files are included for the major cross sections. Much of the present evaluation is taken over from ENDF/B-IV and ENDF/B-V; emphasis is placed on updates for ENDF/B-VI. 14 refs., 3 figs