New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission productsHyeong 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
Published online: 21 May 2008
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