Calculating Infinite-medium a-eigenvalue Spectra with Monte Carlo using the Transition Rate Matrix Method... Journal August, 2015
A Full-Core Resonance Self-Shielding Method Using a Continuous-Energy Quasi-One-Dimensional Slowing-Down Solution that Accounts for Temperature-Dependent Fuel Subregions and Resonance Interference Journal July, 2015
THE MODELING OF ADVANCED BWR FUEL DESIGNS WITH THE NRC FUEL DEPLETION CODES PARCS/PATHS Journal June, 2015
A New Equivalence Theory Method for Treating Doubly Heterogeneous Fuel - II: Verifications... Journal May, 2015
Sustainable Thorium Nuclear Fuel Cycles: A Comparison of Intermediate and Fast Neutron Spectrum Systems... Journal April, 2015
A Parallel Multi-Domain Solution Methodology Applied to Nonlinear Thermal Transport Problems in Nuclear Fuel Pins... Journal April, 2015
Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts in Pressurized Water Reactors... Journal January, 2015
Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization... Journal January, 2015
