A neutronic investigation of the use of fully ceramic microencapsulated fuel for Pu/Np burning in PWRs Journal January, 2013
Neutronics and Depletion Methods for Parametric Studies of Fluoride Salt Cooled High Temperature Reactors with Slab Fuel Geometry and Multi-Batch Fuel Management Schemes Journal January, 2013
Verification of a Depletion Method in SCALE for the Advanced High Temperature Reactor Journal January, 2013
Hybrid Monte Carlo/Deterministic Methods for Accelerating Active Interrogation Modeling Journal January, 2013
Determination and Application of Partial Biases in Criticality Safety Validation Journal January, 2013
Criticality Analysis of Assembly Misload in a PWR Burnup Credit Cask (NUREG/CR-6955, ORNL/TM-2004/52) Technical Report January, 2008