Swelling and Fission Gas Release of U-10Mo and U-17Mo Following Neutron Irradiation at 250 – 500°C Journal April, 2025
Corrosion characteristics of silicon carbide fiber-reinforced composites in beryllium-bearing molten fluoride salt Journal March, 2025
Suppression of irradiation hardening in tungsten-coated ferritic steel for fusion reactor blanket applications Journal March, 2025
Origins of radiation-induced optical attenuation in neutron-irradiated single-crystal sapphire at elevated temperatures Journal March, 2025
Design of Silicide-Strengthened Nb–Si–Cr–(Mo) alloys for additive manufacturing Journal March, 2025
Characterization of the Microstructure of Yttrium Hydride under Proton Irradiation Journal February, 2025
Effect of microstructure and neutron irradiation defects on deuterium retention in SiC Journal February, 2025
Hydrogen permeation in iron-chromium-aluminum (FeCrAl) alloys and the effects of microstructure and surface oxide Journal January, 2025
