Neutronics Studies of Uranium-bearing Fully Ceramic Micro-encapsulated Fuel for PWRs Journal December, 2014
Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses... Journal November, 2014
A Validation Study of Pin Heat Transfer for MOX Fuel Based on the IFA-597 Experiments Journal October, 2014
Properties of Inconel 625 Mesh Structures Grown by Electron Beam Additive Manufacturing... Journal October, 2014
A Validation Study of Pin Heat Transfer for UO2 Fuel Based on the IFA-432 Experiments Journal July, 2014
Massively Parallel, Three-Dimensional Transport Solutions for the k-Eigenvalue Problem Journal June, 2014
Applications of nuclear data covariances to criticality safety and spent fuel characterization Journal April, 2014