Comparison of Calculated and Measured Neutron Fluence in Fuel/Cladding Irradiation Experiments in HFIR Conference Paper November, 2011
C5 Benchmark Problem with Discrete Ordinate Radiation Transport Code DENOVO... Journal November, 2011
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predic... Conference Paper September, 2011
Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive Simulation... Journal September, 2011
