Performance assessment of self-interrogation neutron resonance densitometry for spent nuclear fuel assay Journal January, 2013
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
The simultaneous determination of 235U and 239Pu using delayed neutron activation analysis Journal January, 2013
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