Andrew Nelson Section Head, Nuclear Fuel Development Contact NELSONAT@ORNL.GOV All Publications Direct ink writing of aqueous-based Gadolinium (III) oxide slurries Critical response to M. Worrall et al. Published in Annals of Nuclear Energy 207 (2024) 110731... MicroMechanical Response of SiC-OPyC Layer in TRISO Fuel Particles Investigation of UO2 Doped with Fe2O3 Sintered Under a Reducing Atmosphere Statistical fracture behavior of doped UO2 using a ball-on-ring equibiaxial flexure test method Interface stability of ultrasonic additively manufactured Zircaloy-4 during hydrothermal corrosion High Plasticity in Refractory Composite Fabrication by Ultrasonic Additive Manufacturing Hydrogen embrittlement of Zircaloy-4 fabricated by ultrasonic additive manufacturing Viability of miniature discs in LFA-427 Modeling and design of a separate effects irradiation test targeting fission gas release from Cr-doped UO2... Raman spectroscopy of uranium nitride kernels Microstructural characterization and equibiaxial flexural strength of CeO2 and Ti-doped CeO2 Ability of x-ray computed tomography to resolve critical flaw size in laser-based, paste stereolithography ceramic printing of alumina Using in situ UO2 bicrystal sintering to understand grain boundary dislocation nucleation kinetics and creep 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 tub... 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 matrix 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
