Andrew Nelson Section Head, Nuclear Fuel Development Contact NELSONAT@ORNL.GOV All Publications Hydrogen effects on thermal diffusivity and electrical resistivity of zircaloy cladding Nuclear fuel irradiation testbed for nuclear security applications Prospects for additive manufacturing of nuclear fuel forms... Accelerated fission rate irradiation design, pre-irradiation characterization, and adaptation of conventional PIE methods for U-10Mo and U-17Mo Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys Irradiation of Isotopically Tagged UO2 Fuel for Intentional Forensics Purposes Thermal Optimization of UO2-Mo Fuel Using Sensitivity Analysis and Genetic Algorithms On the Role of Microstructure on the Burst Properties of Oxide Dispersion Strengthened FeCrAl Alloys During Simulated Loss-of-Coolant Accident Conditions In situ synchrotron tensile investigations on ultrasonic additive manufactured (UAM) zirconium Creep behavior of an additively manufactured 9Cr steel in the as-built condition Hydrothermal corrosion and steam oxidation behavior comparison of UAM and conventional Zry-4 Thermal conductivity evaluation of ion irradiated Si3N4 and ZrN ceramics using spatial domain thermoreflectance Synthesis of U3O8 and UO2 microspheres using microfluidics On the efficacy of post-build thermomechanical treatments to improve properties of Zirconium fabricated using ultrasonic additive manufacturing 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... Report summarizing demonstration of thermal conductivity measurement methods for coated zirconium cladding Properties and microstructure evolution of silicon nitride and zirconium nitride following Ni ion irradiation Identifying chemically similar multiphase nanoprecipitates in compositionally complex non-equilibrium oxides via machine learning 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 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
