MECHANICAL BEHAVIOR OF FRESH, HYDRIDED, AND Cr-COATED CLADDING TUBES AND SUB-SIZED FLAT SPECIMENS Conference Paper October, 2024
METHOD FOR EXPOSING IRRADIATED FUEL CLADDING TO RAPID THERMAL TRANSIENTS Conference Paper October, 2024
Modeling and design of a separate effects irradiation test targeting fission gas release from Cr-doped UO2... Journal September, 2024
NSUF BOILER Pre-Irradiation Characterization and High Flux Isotope Reactor Experiment Design ORNL Report September, 2024
In-service Oxidation and IASCC in High Fluence Baffle-Former Bolts Retrieved from a Westinghouse PWR... ORNL Report September, 2024
ROADRUNNER MiniFuel Experiment - Irradiation Target Design and Sample Characterization ORNL Report September, 2024
Community Data Contribution to M.E.T.A. with ATF-relevant Hydrided Zr cladding (Coated and Uncoated) ORNL Report September, 2024
Post-Irradiation Examination on Absorber Material Specimens Irradiated in the High Flux Isotope Reactor... ORNL Report September, 2024
