Massively Parallel, Three-Dimensional Transport Solutions for the k-Eigenvalue Problem Journal June, 2014
Applications of nuclear data covariances to criticality safety and spent fuel characterization Journal April, 2014
A Monte Carlo Synthetic-Acceleration Method for Solving the Thermal Radiation Diffusion Equation Journal February, 2014
FW-CADIS Method for Global and Semi-Global Variance Reduction of Monte Carlo Radiation Transport Calculations Journal January, 2014
Neutronics and Depletion Methods for Parametric Studies of Fluoride Salt Cooled High Temperature Reactors with Slab Fuel Geom... Journal September, 2013
Verification of a Depletion Method in SCALE for the Advanced High Temperature Reactor... Journal September, 2013
A Statistical Sampling Method for Uncertainty Analysis with SCALE and XSUSA... Journal September, 2013
