Andrew Nelson Section Head, Nuclear Fuel Development Contact NELSONAT@ORNL.GOV All Publications 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 Deformation and fracture characteristics of zirconium plate produced via ultrasonic additive manufacturing MICROSTRUCTURAL ANALYSIS OF IRON-CHROMIUM-ALUMINUM SAMPLES EXPOSED TO LOCA-TYPE CONDITIONS FOLLOWED BY QUENCH Oxidation Behavior Comparison of UAM and Conventional Zry-4 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 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 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 Microstructure Investigation and Mechanical Properties of Coated Zircaloy Cladding Studies on Enhanced Spatial Control with Low Enriched Uranium in Plate-Type Fuels Fabrication of UN-Mo CERMET Nuclear Fuel Using Advanced Manufacturing Techniques Full Core Large Break LOCA Fuel System Uncertainty Analysis for a PWR Containing High Burnup Fuel Uranium Carbide Properties for Advanced Fuel Modeling – A Review Instability of U3Si2 in pressurized water media at elevated temperatures Architecture and properties of TCR fuel form Ball-on-ring test validation for equibiaxial flexural strength testing of engineered ceramics... Irradiation-induced amorphization of Fe-Y-based second phase particles in accident-tolerant FeCrAl alloys Aluminum-doped U3Si2 composite fuels with enhanced oxidation resistance Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering Development of Standardized Property Requirements, Measurement Methods, and Reporting Guidance for Coatings Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 … 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
