Portrait

Kory D Linton

Senior 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

The state of the art for neutron irradiation experiments from the perspective of the High Flux Isotope Reactor (HFIR)

Strength and ductility of additively manufactured 316L stainless steel: Impact of neutron irradiation and data variability

ROADRUNNER MiniFuel Experiment: Readiness for Insertion

The impact of chromium coatings on Zircaloy cladding deformation behavior under reactivity-initiated accident-like mechanical loading conditions

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

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)

ROADRUNNER MiniFuel Experiment - Irradiation Target Design and Sample Characterization

Fatigue Testing and Characterization of Pre-hydrided Zircaloy-4 Cladding Tubes

Report on RIA Relevant Modified Burst Testing of ATF Cladding Materials

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

UCO TRISO Minifuel FY23 NSUF-Kairos Power Post-Irradiation Examination Status Report...

Mechanical properties of Zircaloy cladding tubes and contributions to M.E.T.A. mechanical property database