Evaluation of neutron-induced reactions on sup 2 sup 3 sup 6 Pu for JENDL-3.3

Cross sections and energy-angular distributions of emitted neutrons were evaluated for the neuron-incident reactions on sup 2 sup 3 sup 6 Pu in the incident energy range of 10 eV to 20 MeV by using a statistical model combined with a coupled channel optical model. The calculated results were compiled to the latest evaluated nuclear data library JENDL-3.3 in the ENDF-6 format. The unresolved resonance region is assumed to be from 10 eV to 30 keV, and the averaged resonance parameters were obtained to reproduce the calculated cross sections. Maxwell temperature for fission neutron spectra were estimated from a systematics with a correction for prefission neutrons.