Assembly of MiniFuel Targets for Irradiation of TRISO Fuel Compacts in the High Flux Isotope Reactor ORNL Report July, 2021
Influence of neutron irradiation on Al-6061 alloy produced via ultrasonic additive manufacturing Journal July, 2021
Correlations of the Steam Oxidation Rate Constant of BWR Alloy Zircaloy-2 at 800–1400 °C Journal July, 2021
Demonstration of Novel Post-Irradiation Examination Capabilities on MiniFuel Disk Specimens ORNL Report July, 2021
Correlations of the Steam Oxidation Rate Constant of BWR Alloy Zircaloy-2 at 800–1400 °C Journal July, 2021
Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation Journal June, 2021
Performance of FeCrAl Accident Tolerant Fuel Cladding under Reactivity Insertion Accident Condition Testing Conference Paper June, 2021
Current Status of HFIR Irradiation Testing Supporting the Transformational Challenge Reactor Conference Paper June, 2021
Handbook on the Material Properties of Yttrium Hydride for High Temperature Moderator Applications... ORNL Report June, 2021
Full Core Large Break LOCA Fuel System Uncertainty Analysis for a PWR Containing High Burnup Fuel Conference Paper June, 2021
