Irradiation Testing of Silicon Carbide Joint Specimens in the High Flux Isotope Reactor Conference Paper December, 2021
Characterization of Fuel and Cladding In and Near the Pellet-Pellet Gap of a High-Burnup Pressurized Water Reactor Fuel Rod Conference Paper October, 2021
FeCrAl Accident Tolerant Fuel Cladding: Insights from a Decade of Development Conference Paper September, 2021
Microstructural characterization of neutron irradiated mineral concrete aggregates Conference Paper July, 2021
High Temperature Thermal Neutron Scattering Measurements and Evaluation of YHx for the Transformational Challenge Reactor Conference Paper June, 2021
Current Status of HFIR Irradiation Testing Supporting the Transformational Challenge Reactor Conference Paper June, 2021
Recent advances on microstructural characterization and modeling of nuclear graphite Conference Paper June, 2021
Overview of the multifaceted activities towards development and deployment of nuclear-grade FeCrAl Alloys ... Conference Paper September, 2016
