U.S. Commercial Spent Nuclear Fuel Assembly Characteristics: 1968-2013 (NUREG/CR-7227) Technical Report January, 2016
Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks Journal January, 2016
Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit (NUREG/CR-7224, ORNL/TM-2015/544) Technical Report January, 2016
Taking A Fresh Look at Boiling Heat Transfer on the Road to Improved Nuclear Economics and Efficiency Journal January, 2016
Assessment of Pellet-Clad Interaction Indicators in Watts Bar Unit 1, Cycles 1-3 Using VERA Conference Proceeding January, 2016
High-Fidelity Heat Deposition Analysis for the High Flux Isotope Reactor Conference Proceeding January, 2016
Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code Journal January, 2016