FeCrAl Accident Tolerant Fuel Cladding: Insights from a Decade of Development Conference Paper September, 2021
Electron microscopy characterization of the fuel-cladding interaction in medium burnup annular fast reactor MOX Journal August, 2021
Complexity of deformation mechanism in neutron-irradiated 304L austenitic stainless steel at microstructural scale Journal August, 2021
Quantification of in-grain lattice gradient in neutron irradiated 304L SS during deformation using insitu EBSD... Conference Paper August, 2021
Fracture Toughness Characterization of Generation II FeCrAl Alloys after ~18 dpa Irradiation ORNL Report August, 2021
Development and Implementation of Digital Image Correlation for Out-of-Cell Burst Testing ORNL Report August, 2021
Mechanical Properties of Additive Manufacturing 316L Stainless Steel Before and After Neutron Irradiation - FY 2021 ORNL Report August, 2021
Assembly of MiniFuel Targets for Irradiation of U-Mo Fuel Specimens in the High Flux Isotope Reactor... ORNL Report August, 2021
Determining failure properties of as-received and hydrided unirradiated Zircaloy-4 from ring compression tests Journal July, 2021
