Key results from irradiation and post-irradiation examination of AGR-1 UCO TRISO fuel Conference Paper November, 2016
Rationalization of anisotropic mechanical properties of Al-6061 fabricated using ultrasonic additive manufacturing... Journal September, 2016
Spent Nuclear Fuel Dynamic Performance under Normal Condition of Transport Conference Paper September, 2016
Neutron energy spectrum influence on irradiation hardening and microstructural development of tungsten Journal July, 2016
Microstructural Stability and Mechanical Behavior of FeNiMnCr High Entropy Alloy under Ion Irradiation Journal July, 2016
Advancements in FeCrAl Alloys for Enhanced Accident Tolerant Fuel Cladding for Light Water Reactors Conference Paper June, 2016
Characterization of Materials Properties and Crack Propagation Mechanisms in Damaged Alloy 718 Leaf Springs Following Commerc... Conference Paper May, 2016
Summary of the Workshop on Molten Salt Reactor Technologies Commemorating the 50th Anniversary of the Startup of the Molten S... Conference Paper April, 2016
