Measurement of the neutron-induced fission cross-section of Am-243 relative to U-235 from 0.5 to 20 MeV Journal December, 2011
ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data ... Journal December, 2011
ENDF/B-VII.1 Neutron Cross Section Data Testing with Critical Assembly Benchmarks and Reactor Experiments... Journal December, 2011
Covariances of Evaluated Nuclear Cross Section Data for (232)Th, (180,182,183,184,186)W and (55)Mn Journal December, 2011
C5 Benchmark Problem with Discrete Ordinate Radiation Transport Code DENOVO... Journal 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
Investigation of Backscatter X-ray imaging techniques for Uranium Dioxide Fuel Rods Journal 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
