Andrew T Nelson Section Head, Nuclear Fuel Development Contact nelsonat@ornl.gov | 865.241.7330 All Publications Creep behavior of an additively manufactured 9Cr steel in the as-built condition... Additive manufacturing of ceramic materials for energy applications: Road map and opportunities... Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures... Oxidation kinetics of SPS-densified U 3 Si 2 fuels—Microstructure impact... Properties and microstructure evolution of silicon nitride and zirconium nitride following Ni ion irradiation... Report summarizing demonstration of thermal conductivity measurement methods for coated zirconium cladding... Identifying chemically similar multiphase nanoprecipitates in compositionally complex non-equilibrium oxides via machine lear... High volume packing fraction TRISO-based fuel in light water reactors... High-temperature compressive creep tests of U3Si2 with spark plasma sintering: Experiments and finite element modeling... Accuracy of stereolithography printed alumina with digital light processing... Ultrasonic additive manufacturing of zirconium: Pilot results... Deformation and fracture characteristics of zirconium plate produced via ultrasonic additive manufacturing... Impact of Coating Defects on Performance of Coated Zirconium Cladding... The U.S. Accident Tolerant Fuels Program — Update on a National Initiative... Transverse Rupture Strength of Uranium Dioxide... MICROSTRUCTURAL ANALYSIS OF IRON-CHROMIUM-ALUMINUM SAMPLES EXPOSED TO LOCA-TYPE CONDITIONS FOLLOWED BY QUENCH... Oxidation Behavior Comparison of UAM and Conventional Zry-4... Assembly of MiniFuel Targets for Irradiation of U-Mo Fuel Specimens in the High Flux Isotope Reactor... Fracture Toughness Characterization of Generation II FeCrAl Alloys after ~18 dpa Irradiation... Fabrication and Characterization of Single-Particle Compacts... Microstructural and crystallographic effects of sol-gel synthesized Ti-doped UO2 sintered under reducing conditions... FY21 burst activities with coated Zircaloy-4 under accident conditions... Correlations of the Steam Oxidation Rate Constant of BWR Alloy Zircaloy-2 at 800–1400 °C... Correlations of the Steam Oxidation Rate Constant of BWR Alloy Zircaloy-2 at 800–1400 °C... Full Core Large Break LOCA Fuel System Uncertainty Analysis for a PWR Containing High Burnup Fuel... Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Page 3 … Next page ›› Last page Last » Key Links Curriculum Vitae ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section