Andrew T Nelson Section Head, Nuclear Fuel Development Contact nelsonat@ornl.gov | 865.241.7330 All Publications Raman spectroscopy of uranium nitride kernels Parallel Irradiation Testing to Support Accelerated Down-Selection of Advanced Fuels... 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 A review of neutronics and thermal hydraulics–based screening methods applied to accelerated nuclear fuel qualification... Sensitivity of UO2 fuel performance to microstructural evolutions driven by dilute additives Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment Analysis of orientation-dependent deformation mechanisms in additively manufactured Zr using in-situ micromechanical testing: Twinning and orientation gradient 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 Irradiation of Isotopically Tagged UO2 Fuel for Intentional Forensics Purposes... Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing... Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys... 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... 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... Creep behavior of an additively manufactured 9Cr steel in the as-built condition... 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