Andrew T Nelson Section Head, Nuclear Fuel Development Contact nelsonat@ornl.gov | 865.241.7330 All Publications Raman spectroscopy of uranium nitride kernels Heat transfer optimization of uo2-mo fuel using genetic algorithms... Equibiaxial flexural strength determination of UO2 using a ball-on-ring test Irradiation creep measurement and microstructural analysis of chromium nitride–coated zirconium alloy using pressurized tubes Microstructure dependent burst behavior of oxide dispersion–strengthened FeCrAl cladding Sensitivity of UO2 fuel performance to microstructural evolutions driven by dilute additives A review of neutronics and thermal hydraulics–based screening methods applied to accelerated nuclear fuel qualification... Analysis of orientation-dependent deformation mechanisms in additively manufactured Zr using in-situ micromechanical testing: Twinning and orientation gradient Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment Design of a MiniFuel Irradiation Experiment to Study Fuel Performance Phenomena in Ceramic Fuels Fission gas retention of densely packed uranium carbonitride tristructural-isotropic fuel particles in a 3D printed SiC matri... Nuclear fuel irradiation testbed for nuclear security applications Hydrogen effects on thermal diffusivity and electrical resistivity of zircaloy cladding Accelerated fission rate irradiation design, pre-irradiation characterization, and adaptation of conventional PIE methods for U-10Mo and U-17Mo Prospects for additive manufacturing of nuclear fuel forms Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys... Irradiation of Isotopically Tagged UO2 Fuel for Intentional Forensics Purposes... Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing... 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... 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 addi... Pagination Current page 1 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
