A Pulse-Controlled Modified Burst Test Instrument for Accident-Tolerant Fuel Cladding ... Journal June, 2017
Determining the minimum required uranium carbide content for HTGR UCO fuel kernels... Journal June, 2017
Design, properties, and weldability of advanced oxidation resistant FeCrAl alloys ... Journal May, 2017
Investigation of High-temperature Oxidation Kinetics and Residual Ductility of Oxidized Samples of Sponge-based E110 Alloy Cladding Tubes Conference Paper May, 2017
Characterization of local hydride re-orientation in high burn-up PWR fuel rods induced by high pressure at high temperatures Conference Paper May, 2017
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: motivation and overview... Journal May, 2017
The Mechanical Response of Advanced Claddings during Proposed Reactivity Initiated Accident Conditions... Conference Paper February, 2017
Structure and Mechanical Properties of Improved Cast Stainless Steels for Nuclear Applications Journal January, 2017
INITIAL RESULTS FROM SAFETY TESTING OF US AGR-2 IRRADIATION TEST FUEL Conference Paper November, 2016
Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test Conference Paper November, 2016
