Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core–Concrete Interaction... Conference Paper August, 2015
Heat up and potential failure of BWR upper internals during a severe accident Conference Paper August, 2015
LAMDA: Irradiated-Materials Microscopy at Oak Ridge National Laboratory Conference Paper August, 2015
Effect of specimen size and grain orientation on the mechanical and physical properties of NBG-18 nuclear graphite... Journal July, 2015
Coating Development on Graphite-Based Composite Fuel for Nuclear Thermal Propulsion... Conference Paper July, 2015
Extrusion Development of Graphite-Based Composite Fuel for Nuclear Thermal Propulsion Conference Paper July, 2015
High dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites, Part 1: Microstructural evaluations Journal July, 2015
THE MODELING OF ADVANCED BWR FUEL DESIGNS WITH THE NRC FUEL DEPLETION CODES PARCS/PATHS Journal June, 2015
