Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response... Journal December, 2014
Neutronics Studies of Uranium-bearing Fully Ceramic Micro-encapsulated Fuel for PWRs Journal December, 2014
Verification of Doubly-Heterogeneous Self-Shielding Method based on Equivalance Theory Conference Paper November, 2014
Determination of Bias, Bias Uncertainty, and Coverage using Data Assimilation 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
