Neutronics Studies of Uranium-Bearing Fully Ceramic Micro-Encapsulated Fuel for PWRs Journal January, 2014
A Neutronic Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Pu/Np Burning in PWRs Journal January, 2014
Massively Parallel, Three-Dimensional Transport Solutions for the k-Eigenvalue Problem Journal January, 2014
Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Journal January, 2014
Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response Journal January, 2014
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