Neutronics Studies of Uranium-Bearing Fully Ceramic Micro-Encapsulated Fuel for PWRs Journal January, 2014
A Neutronic Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Pu/Np Burning in PWRs Journal January, 2014
Massively Parallel, Three-Dimensional Transport Solutions for the k-Eigenvalue Problem Journal January, 2014
Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Journal January, 2014
Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response Journal January, 2014
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
The simultaneous determination of 235U and 239Pu using delayed neutron activation analysis 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