On the unresolved resonance region representation of neutron induced cross sections

The accurate representation of neutron cross sections in the unresolved resonance region is of interest for the calculation of the Doppler coefficient of reactivity and self-shielded group cross -section sets for fast reactors. Customarily, the cross sections in the unresolved resonance region are described on the basis of the statistical theory of nuclear reactions, by specifying average values and distribution functions for the resonance parameters. Resonance self-shielding factors can then be calculated by the appropriate statistical techniques. In this work we review the unresolved resonance region formalism in the light of the availability of new high-energy resolution measurements. 8 refs., 3 figs., 2 tabs