UNF-ST&DARDS: A Unique Tool for Automated Characterization of Spent Nuclear Fuel and Related Systems... Conference Paper September, 2016
An Advanced Materials Irradiation Facility for Materials and Fuels Irradiations at the High Flux Isotope Reactor ... Conference Paper September, 2016
Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks Journal August, 2016
Analysis of Operational and Safety Performance for Candidate Accident Tolerant Fuel and Cladding Concepts Conference Paper July, 2016
Materials Irradiation Facility (MIF) at the High Flux Isotope Reactor (HFIR)... Conference Paper June, 2016
Core Design Characteristics of the Fluoride Salt-Cooled High Temperature Demonstration Reactor Conference Paper April, 2016
Thermal Modeling Sensitivities with COBRA-SFS for Vertical Dry Casks with Limited Internal Convection... Conference Paper November, 2015
Analysis of the FeCrAl Accident Tolerant Fuel Concept Benefits during BWR Station Blackout Accidents Conference Paper August, 2015
Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core–Concrete Interaction... Conference Paper August, 2015
