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
Effects of chemical alternation on damage accumulation in concentrated solid-solution alloys... Journal June, 2017
Design, properties, and weldability of advanced oxidation resistant FeCrAl alloys ... Journal May, 2017
The effect of injected interstitials on void formation in self-ion irradiated nickel containing concentrated solid solution a... Journal May, 2017
Corrections to ``Atom probe tomography characterization of neutron irradiated surveillance samples from the R. E. Ginna react... Journal May, 2017
A combined APT and SANS investigation of αʹ phase precipitation in neutron-irradiated model 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