Consolidating Spent Nuclear Fuel Related Data into a Unified Database... Conference Paper November, 2016
UNF-ST&DARDS: A Unique Tool for Automated Characterization of Spent Nuclear Fuel and Related Systems... Conference Paper September, 2016
Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks Journal August, 2016
Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code Journal February, 2016
