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
A New Approach to Fork Measurements Data Analysis by RADAR-CRISP and ORIGEN Integration Journal January, 2014