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
Effects of chemical alternation on damage accumulation in concentrated solid-solution alloys Journal June, 2017
The Plan for Post-Irradiation Examination of Zion Reactor Pressure Vessel Beltline Materials Conference Paper June, 2017
Development of Next Generation Tempered and ODS Reduced Activation Ferritic/Martensitic Steels for Fusion Energy Applications... Journal June, 2017
JECS - Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700°C Journal June, 2017
A Pulse-Controlled Modified Burst Test Instrument for Accident-Tolerant Fuel Cladding ... Journal June, 2017
Creep Resistance and Fracture Toughness of Recently-Developed Optimized Grade 92 and Its Weldments for Advanced Fast Reactors... Conference Paper June, 2017
