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
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