Development of the SCK CEN reference datasets for spent fuel safeguards research and development.

ABSTRACT: A set of reference spent fuel libraries has been organized in datasets containing the material composition and radiation emission (i.e. neutrons and gamma-rays) of spent fuel. The data was obtained with computer simulations using the ORIGEN-ARP code, which is part of the SCALE 6.1 package. Both fuel assembly geometries for Pressurized Water Reactors (PWR 17 × 17) and Boiling Water Reactors (BWR 8 × 8) are included in the datasets, and for each geometry both uranium oxide (UO2) and mixed oxide (MOX) fuel materials are considered. The datasets contain the information for spent fuel with a broad range of initial enrichment (UO2 fuel) or initial Pu content (MOX fuel), discharge burnup, and cooling time. For each simulation the neutron spectra, divided into contributions from (α,n) reactions, s

SUBMITTER: Rossa R 

PROVIDER: S-EPMC7153292 | biostudies-literature | 2020 Jun

REPOSITORIES: biostudies-literature