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
Consequence Analysis of Spent Nuclear Fuel Reconfiguration Scenarios... Conference Paper August, 2013
