Development of Continuous-Energy Eigenvalue Sensitivity Coefficient Calculation Methods in the Shift Monte Carlo Code... Conference Paper April, 2012
Re-estimation of Nuclear Data and JEFF 3.1.1 Uncertainty Calculations... Conference Paper April, 2012
Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations... Conference Paper April, 2012
Neutron-induced fission cross section of Cm-245: New results from data taken at the time-of-flight facility n_TOF... Journal March, 2012
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
A Cut-Cell Approach for 2D Cartesian Meshes that Preserves Orthogonal Grid Sweep Ordering... Conference Paper November, 2011