We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.
0, of recommended nuclear data for advanced nuclear science and technology applications …

Uncertainties in the predicted isotopic concentrations in spent nuclear fuel represent one of
the largest sources of overall uncertainty in criticality calculations that use burnup credit. The …

This report proposes and documents a computational benchmark problem for the estimation
of the additional reactivity margin available in spent nuclear fuel (SNF) from fission products …

This report investigates trends in the radiological decay properties and changes in relative
nuclide importance associated with increasing enrichments and burnup for spent LWR fuel …

Abstract Dynamic Mode Decomposition (DMD) was used to produce surrogates for the
evolution of spatially-varying nuclide compositions in a TRIGA reactor. First, the method was …

This report presents studies performed to support the development of a technically justifiable
approach for addressing the axial-burnup distribution in pressurized-water reactor (PWR) …

This report has been prepared to review relevant background information and provide
technical discussion that will help initiate a PIRT (Phenomena Identification and Ranking …

This paper proposes a methodology for burnup credit of spent nuclear fuel (SNF) pool
storage based on the axial burnup of the fuel assemblies. Following the NRC guidance and …

Monte Carlo sampling is frequently employed for uncertainty quantification in depletion
calculations. Several assumptions are needed to perform this analysis. In this work, an …

Isotopic characterization of spent fuel via depletion and decay calculations is necessary for
determination of source terms for subsequent system analyses involving heat transfer …