Development of a SCALE Model for High Flux Isotope Reactor Cycle 400 (ORNL/TM-2011-367) Technical Report January, 2012
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (keff) Predictions (NUREG/CR-7109, ORNL/TM-2011/514) Technical Report January, 2012
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
Application of the SCALE TSUNAMI Tools for the Validation of Criticality Safety Calculations Involving 233U (ORNL/TM-2008/196) Technical Report January, 2009
Development and Testing of ENDF/B-VI.8 and ENDF/B-VII.0 Coupled Neutron-Gamma Libraries for SCALE 6 (NUREG/CR-6990, ORNL/TM-2008/047) Technical Report January, 2009
Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel Technical Report January, 2000
Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel (NUREG/CR-6665, ORNL/TM-1999/303) Technical Report January, 2000