Mechanical properties of SiC composites neutron irradiated under light water reactor relevant temperature and dose conditions Journal July, 2017
Effects of chemical alternation on damage accumulation in concentrated solid-solution alloys Journal June, 2017
Post Irradiation Examination of SiC Tube Subjected to Simultaneous Irradiation and Radial High Heat Flux Conference Paper June, 2017
Hydride Microstructure at the Metal-Oxide Interface of Zircaloy-4 from H.B. Robinson Nuclear Reactor Conference Paper June, 2017
JECS - Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700°C Journal June, 2017
The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution a... Journal May, 2017
Design, properties, and weldability of advanced oxidation resistant FeCrAl alloys ... Journal May, 2017
Experimental Design and Analysis for Irradiation of SiC/SiC Composite Tubes under a Prototypic High Heat Flux Journal May, 2017
