Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Difficult Shielding Problems Journal January, 2015
A Method for Including External Feed in Depletion Calculations with CRAM and Implementation into ORIGEN Journal January, 2015
The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation Journal January, 2015
Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization Journal January, 2015
A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN Journal January, 2015
Bias Estimates Used in Lieu of Validation of Fission Products and Minor Actinides in MCNP Keff Calculations for PWR Burnup Credit Casks (NUREG/CR-7205, ORNL/TM-2012/544) Technical Report January, 2015
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation-Calvert Cliffs, Takahama, and Three Mile Island Reactors (NUREG/CR-6968, ORNL/TM-2008/071) Technical Report January, 2010
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation-ARIANE and REBUS Programs (UO2 Fuel) (NUREG/CR-6969, ORNL/TM-2008/072) Technical Report January, 2010
Validation of SCALE 5 Decay Heat Predictions for LWR Spent Nuclear Fuel (NUREG/CR-6972, ORNL/TM-2008/015) Technical Report January, 2010
Technical Basis for a Proposed Expansion of Regulatory Guide 3.54-Decay Heat Generation in an Independent Spent Fuel Storage Installation (NUREG/CR-6999, ORNL/TM-2007/231) Technical Report January, 2010