Modeling data for SFCOMPO benchmarks supporting burnup code validation

Abstract

Destructive radiochemical assay (RCA) measurements were performed at Oak Ridge National Laboratory for 16 fuel samples selected from 6 sister fuel rods from 5 assemblies of the North Anna pressurized water reactor (PWR). These new measurement data help filling in existing gaps at high burnups in the validation basis for burnup codes used to calculate nuclide inventories in irradiated nuclear fuels, and facilitate understanding the capabilities of burnup methods, codes, and associated nuclear data. Inclusion of the new 16 samples PWR data to the over 150 existing samples in the SFCOMPO international database of spent fuel compositions will help expanding the validation basis. It will facilitate user-friendly access to end-users, including US industry, to these specific 16 samples data, in conjunction with all the other wealth of data within SFCOMPO within a consistent framework, therefore increasing the effectiveness of data application for burnup codes validation. The fuel samples modeling data that are needed to develop adequate SFCOMPO benchmark models supporting burnup codes validation are summarized herein.