Open Access
Issue
ND 2007
2007
Article Number 171
Number of page(s) 4
Section Thermal and resonance range
DOI https://doi.org/10.1051/ndata:07542
Published online 17 June 2008
International Conference on Nuclear Data for Science and Technology 2007
DOI: 10.1051/ndata:07542

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Hyeong Il Kim1, Young-Ouk Lee1, Mike Herman2, Said F. Mughabghab2, Pavel Oblozinský2 and Dimitri Rochman2

1  Nuclear Data Evaluation Laboratory, Korea Atomic Energy Research Institute, Daejeon 305-353, Korea
2  National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000, USA

hikim@kaeri.re.kr

Published online: 21 May 2008

Abstract
Neutron cross sections for fission products play an important role not only in the design of extended burn-up core and fast reactors, but also in the study of the backend fuel cycle and the criticality analysis of spent fuel. New evaluations for the ENDF/B-VII.0 library were performed by the KAERI-BNL collaboration for the following 32 fission products: 95Mo, 101Ru, 103Rh, 105Pd, 109Ag, 131Xe, 133Cs, 141Pr, and complete isotope chains of 142-148,150Nd, 144,147,148-154Sm, and 156,158,160-164Dy. The evaluations cover a large amount of reaction channels, from 10-5 eV to 20 MeV, including thermal, resolved, unresolved resonance regions, and fast neutron region.



© CEA 2008

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