Kory Linton Sr. Program Manager, Nuclear Fuels and Materials Contact 865.241.2767 | LINTONKD@ORNL.GOV All Publications High-temperature steam oxidation study of irradiated FeCrAl defueled specimens... Failure analysis of nuclear transient-tested UN tristructural isotropic fuel particles in a 3D printed SiC matrix Simulation of a TRISO MiniFuel irradiation experiment with data-informed uncertainty quantification Fission gas retention of densely packed uranium carbonitride tristructural-isotropic fuel particles in a 3D printed SiC matrix Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing Mechanical Behavior of Additively Manufactured and Wrought 316L Stainless Steels Before and After Neutron Irradiation Phase stability and microstructure of neutron-irradiated substoichiometric yttrium dihydrides MECHANICAL BEHAVIOR OF FRESH, HYDRIDED, AND Cr-COATED CLADDING TUBES AND SUB-SIZED FLAT SPECIMENS Irradiation and Mechanical Testing of Chromium-Coated M5Framatome Cladding Tubes ROADRUNNER MiniFuel Experiment - Irradiation Target Design and Sample Characterization Post-Irradiation Examination on Absorber Material Specimens Irradiated in the High Flux Isotope Reactor... NSUF BOILER Pre-Irradiation Characterization and High Flux Isotope Reactor Experiment Design Community Data Contribution to M.E.T.A. with ATF-relevant Hydrided Zr cladding (Coated and Uncoated) Report on RIA Relevant Modified Burst Testing of ATF Cladding Materials Fatigue Testing and Characterization of Pre-hydrided Zircaloy-4 Cladding Tubes Hydrogen motion in near stoichiometric yttrium dihydride at elevated temperatures Residual Stress Measurements of Cr-coated Cladding Impact of nano-scale cavities on hydrogen storage and retention in yttrium hydride... AFC FY 2023 HFIR Irradiation Test Matrix – Supported by the Design of a Ring Specimen Irradiation Vehicle Mechanical properties of Zircaloy cladding tubes and contributions to M.E.T.A. mechanical property database AMMT FY23 HFIR Irradiation Test Matrix – Supported by the Design of a Miniature Bend Bar Irradiation Vehicle UCO TRISO Minifuel FY23 NSUF-Kairos Power Post-Irradiation Examination Status Report... Irradiation Testing of Fully Ceramic Microencapsulated (FCM) Fuel Compacts in the High Flux Isotope Reactor Preliminary Analysis of Reactivity Initiated Accident Separate Effects Mechanical Tests on Chromium-Coated Zirconium Cladding Mechanical Properties of Additively Manufactured 316L Stainless Steel Before and After Neutron Irradiation–FY23 Pagination Current page 1 Page 2 Page 3 … Next page ›â¶Äº Last page Last » Key Links Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division
