A Parallel Multi-Domain Solution Methodology Applied to Nonlinear Thermal Transport Problems in Nuclear Fuel Pins... Journal April, 2015
Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts in Pressurized Water Reactors... Journal January, 2015
Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization... Journal January, 2015
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
Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses... Journal November, 2014
Properties of Inconel 625 Mesh Structures Grown by Electron Beam Additive Manufacturing... Journal October, 2014
