Application of Artificial Neural Networks for Reliable Nuclear Data for Nonproliferation Modeling and Simulation... Journal December, 2016
Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks Journal August, 2016
Uncertainty Quantification in (α,n) Neutron Source Calculations for an Oxide Matrix Journal April, 2016
Improved Mixed Oxide Fuel Calculations with the Evaluated Nuclear Data Library JEFF-3.2... Journal February, 2016
Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code Journal February, 2016
Isotopic molybdenum total neutron cross section in the unresolved resonance region Journal August, 2015
Cross section measurements for neutron inelastic scattering and the (n, 2ny) reaction on 206Pb... Journal June, 2015
Exploration of direct neutron capture with covariant density functional theory inputs... Journal April, 2015
