Implementation of a Spacer Grid Rod Thermal-Hydraulic Reconstruction (ROTHCON) Capability into the Thermal-Hydraulic Subchannel Code CTF Journal April, 2019
Neutronic and thermal-hydraulic feasibility studies for High Flux Isotope Reactor conversion to low-enriched uranium silicide... Journal March, 2019
Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit Journal February, 2019
A composite position independent monitor of reactor fuel irradiation using Pu, Cs, and Ba isotope ratios Journal December, 2018
Modified Point-Kinetics Model for Neutron Precursors and Fission Product Behavior for Fluid-Fueled Molten Salt Reactors Journal November, 2018
Application of the Denovo Discrete Ordinates Radiation Transport Code to Large-Scale Fusion Neutronics... Journal October, 2018
