Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts in Pressurized Water Reactors Journal January, 2015
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
STARBUCS: A prototypic SCALE Control Module for Automated Criticality Safety Analyses Using Burnup Credit (NUREG/CR-6748, ORNL/TM-2001/33) Technical Report January, 2001