Determining Initial Enrichment, Burnup, and Cooling Time of Pressurized-Water Reactor Spent Fuel Assemblies by Analyzing Pass... Journal February, 2016
Thorium Fuel Cycle Pilot Experiences at Oak Ridge National Laboratory Conference Paper November, 2014
ADVANTG Results for a Proposed NDA System for Detecting Pin Diversion from SNF... Conference Paper September, 2014
Tritium Behavior in Zircaloy Cladding from Used Light Water Reactor Fuel Rods... Conference Paper March, 2014
