Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test Journal October, 2017
Key results from irradiation and post-irradiation examination of AGR-1 UCO TRISO fuel Journal September, 2017
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
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: motivation and overview... Journal May, 2017
Structure and Mechanical Properties of Improved Cast Stainless Steels for Nuclear Applications Journal January, 2017
Rationalization of anisotropic mechanical properties of Al-6061 fabricated using ultrasonic additive manufacturing... Journal September, 2016
