Molten Salt Reactor Neutronics and Fuel Cycle Modeling and Simulation with SCALE... Journal March, 2017
A 2-D/1-D Transverse Leakage Approximation Based on Azimuthal, Fourier Moments... Journal February, 2017
A Multigroup, Lumped Parameter MOC Method for Subgroup Self-Shielding in MPACT Conference Paper December, 2016
Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT... Journal December, 2016