Nuclear Data Evaluation for U-233

Abstract

Cross section of neutron-induced reactions on U-233 have been evaluated between 10-5 eV and 20 MeV for the BROND data library. In the thermal and resonance regions evaluation relies on experimental data. Fission and total cross sections have been evaluated on the basis of recent experimental data. A deformed optical potential that fits total, elastic and inelastic cross sections, s- and p-wave strength functions was used to calculate direct inelastic and other cross sections. The available data on total, fission, capture and inelastic scattering are reproduced quite well. Above (n,n’f)reaction threshold preequilibrium emission has been taken into account. The calculated (n,2n) reaction cross section disagrees with available fission spectrum-averaged data and other evaluations. Partial energy distributions of secondary neutrons are given in tabulated form. The evaluated data are compared with ENDL-78 and JENDL evaluations.