Neutronics Studies of Uranium-bearing Fully Ceramic Micro-encapsulated Fuel for PWRs Journal December, 2014
Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response... Journal December, 2014
Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses... Journal November, 2014
Verification of Doubly-Heterogeneous Self-Shielding Method based on Equivalance Theory Conference Paper November, 2014
Fuel Cycle Assessment: Evaluation and Analyses using ORION for US Fuel Cycle Options... Conference Paper November, 2014
Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts in Light Water Reactors Conference Paper November, 2014
Fully Ceramic Microencapsulated (FCM) Fuel in FHRs: A Preliminary Reactor Physics Assessment... Conference Paper November, 2014
Validation of keff Calculations for Boiling-Water Reactor Fuel at Peak Reactivity in Transportation and Storage Casks Conference Paper November, 2014
Evaluation of Peak Reactivity Analysis of Boiling-Water Reactor Fuel in Transportation and Storage Casks... Conference Paper November, 2014
