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
Validation of New Depletion Capabilities and ENDF/B-VII Data Libraries in SCALE Journal January, 2012
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation-Calvert Cliffs, Takahama, and Three Mile Island Reactors (NUREG/CR-6968, ORNL/TM-2008/071) Technical Report January, 2010
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation-ARIANE and REBUS Programs (UO2 Fuel) (NUREG/CR-6969, ORNL/TM-2008/072) Technical Report January, 2010
Validation of SCALE 5 Decay Heat Predictions for LWR Spent Nuclear Fuel (NUREG/CR-6972, ORNL/TM-2008/015) Technical Report January, 2010
Technical Basis for a Proposed Expansion of Regulatory Guide 3.54-Decay Heat Generation in an Independent Spent Fuel Storage Installation (NUREG/CR-6999, ORNL/TM-2007/231) Technical Report January, 2010
SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions (ORNL/TM-2010/44) Technical Report January, 2010