Development of a comprehensive code for nuclear data evaluation, CCONE, and Validation using neutron-induced cross sections for uranium isotopes

Iwamoto, Osamu  

A new theoretical model code CCONE has been developed for the evaluation ofminor actinide. Neutron induced reaction cross sections for uranium isotopes (A=232, 233, 234, 235, 236, 237, 238) for incident energies from 10 keV to 20 MeV were analyzed by the code to check the ability. Reproducibility of the calculation for the various crosssections such as total, fission, capture and (n,2n) reactions weretested using simple parametrizations. The cross secton and neutron emission spectra are compared with the experiments. The results of the calculations show good agreement with the experimental data.