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