Nuclear Science and Engineering · 1974 · 25 citations · 0 references
The purpose of this article is an up-to-date, detailed, and rigorous presentation of the generalized least-squares procedure developed by our group to improve neutron cross-section evaluations, based on direct cross-section measurements by means of integral data. Both discrete and continuous (energy dependent) integral quantities are considered. Explicit expressions are derived for the best estimates of the cross sections in a continuous form, as well as in the multigroup approximation.The procedure is illustrated by results relating to the updated Los Alamos data on spherical metallic critical assemblies and the latest ENDF/B cross-section library. It is demonstrated that by minor modifications of the ENDF/B cross sections, most of the experimental data can be reproduced within their quoted uncertainties.