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

Abstract

Abstract. Neutron cross sections for fission products play an important role not only in the design of extended burnup 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: 95 Nd, 144,147,[148][149][150][151][152][153][154] and 156,158,[160][161][162][163][164] Dy. 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.

EMPIRE: Nuclear Reaction Model Code System for Data Evaluation

“…These results are extensively documented in Ref. [127] and several representative figures can be found in Ref. [1].…”

“…This selection was motivated by the need to improve existing evaluations for materials of importance for a number of applications, including criticality safety, burn-up credit for spent fuel transportation, disposal criticality analysis and the design of advanced fuels. Evaluations for these priority fission products (including full chains of Nd, Sm, and Dy isotopes) were performed under the BNL-KAERI collaboration [127].…”