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 compile...

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Detalles Bibliográficos
Autores principales: Iwamoto, O, Nakagawa, T
Lenguaje:eng
Publicado: 2002
Materias:
Nuclear Physics
Acceso en línea:http://cds.cern.ch/record/747948
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author Iwamoto, O
Nakagawa, T
author_facet Iwamoto, O
Nakagawa, T
author_sort Iwamoto, O
collection CERN
description 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.
id cern-747948
institution Organización Europea para la Investigación Nuclear
language eng
publishDate 2002
record_format invenio
spelling cern-7479482019-09-30T06:29:59Zhttp://cds.cern.ch/record/747948engIwamoto, ONakagawa, TEvaluation of neutron-induced reactions on sup 2 sup 3 sup 6 Pu for JENDL-3.3Nuclear PhysicsCross 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.JAERI-RESEARCH-2002-013oai:cds.cern.ch:7479482002
spellingShingle Nuclear Physics
Iwamoto, O
Nakagawa, T
Evaluation of neutron-induced reactions on sup 2 sup 3 sup 6 Pu for JENDL-3.3
title Evaluation of neutron-induced reactions on sup 2 sup 3 sup 6 Pu for JENDL-3.3
title_full Evaluation of neutron-induced reactions on sup 2 sup 3 sup 6 Pu for JENDL-3.3
title_fullStr Evaluation of neutron-induced reactions on sup 2 sup 3 sup 6 Pu for JENDL-3.3
title_full_unstemmed Evaluation of neutron-induced reactions on sup 2 sup 3 sup 6 Pu for JENDL-3.3
title_short Evaluation of neutron-induced reactions on sup 2 sup 3 sup 6 Pu for JENDL-3.3
title_sort evaluation of neutron-induced reactions on sup 2 sup 3 sup 6 pu for jendl-3.3
topic Nuclear Physics
url http://cds.cern.ch/record/747948
work_keys_str_mv AT iwamotoo evaluationofneutroninducedreactionsonsup2sup3sup6puforjendl33
AT nakagawat evaluationofneutroninducedreactionsonsup2sup3sup6puforjendl33

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