An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predictions (NUREG/CR-7108, ORNL/TM-2011/509) Technical Report January, 2012
Validation of SCALE for High Temperature Gas-Cooled Reactor Analysis (NUREG/CR-7107, ORNL/TM-2011/161) Technical Report January, 2012
Validation of New Depletion Capabilities and ENDF/B-VII Data Libraries in SCALE Journal January, 2012
Use of Sensitivity and Uncertainty Analysis in the Design of Reactor Physics and Criticality Benchmark Experiments for Advanced Nuclear Fuel Journal January, 2005