Microstructure and mechanical properties of heat-treated and neutron irradiated TRISO-ZrC coatings Journal May, 2015
High-Temperature Steam Oxidation Of Accident Tolerant Fuel Cladding Candidate Materials Conference Paper May, 2015
Criticality Safety Assessment for As-loaded Spent Fuel Storage and Transportation Casks... Conference Paper May, 2015
Validation Study for Crediting Chlorine in Criticality Analyses for US Spent Nuclear Fuel Disposition... Conference Paper May, 2015
Recent Fast Neutron Imaging Measurements with the Fieldable Nuclear Materials Identification System... Conference Paper May, 2015
Sustainable Thorium Nuclear Fuel Cycles: A Comparison of Intermediate and Fast Neutron Spectrum Systems... Journal April, 2015
Design of a High Fidelity Core Simulator for Analysis of Pellet Clad Interaction Conference Paper April, 2015
Demonstration of a Full-core Reactivity Equivalence for FeCrAl Enhanced Accident Tolerant Fuel in BWRs... Conference Paper April, 2015
