C5 Benchmark Problem with Discrete Ordinate Radiation Transport Code DENOVO... Journal November, 2011
Comparison of Calculated and Measured Neutron Fluence in Fuel/Cladding Irradiation Experiments in HFIR Conference Paper November, 2011
A Cut-Cell Approach for 2D Cartesian Meshes that Preserves Orthogonal Grid Sweep Ordering Conference Paper November, 2011
Evaluation of Neutron and Gamma Detectors for High-Temperature Well-Logging Applications Conference Paper October, 2011
Hybrid and Parallel Domain-Decomposition Methods Development to Enable Monte Carlo for Reactor Analyses Journal October, 2011
Review of Hybrid (Deterministic/Monte Carlo) Radiation Transport Methods, Codes, and Applications at Oak Ridge National Labor... Journal October, 2011
