Pu for JENDL-3.3Iwamoto, Osamu 
; Nakagawa, Tsuneo
Cross sections and energy-angular distributions of emitted neutrons were evaluated for the neutron-incident reactions on Pu in the incident energy range of 10eV to 20MeV 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 10eV to 30keV, and the averaged resonance parameters were obtained to reproduce the calculated cross sections. Maxwell temperatures for fission neutron spectra were estimated from a systematics with a correction for prefission neutrons.
Language |
: | English |
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Report No. |
: | JAERI-Research 2002-013 |
Pages |
: | 18 Pages |
Publication Year/Month |
: | 2002/07 |
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Paper URL |
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Keywords |
: | Nuclear Data; Evaluation; Pu-236; Neutron; Cross Section; Statistical Model; Optical Model; Coupled Channel Calculation |
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