A Validation Study of Pin Heat Transfer for MOX Fuel Based on the IFA-597 Experiments 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
An Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Transuranic Waste Recycling in Pressurized Water Reac... Journal April, 2014
Characteristics of Commercial Spent Nuclear Fuel: Distributed, Diverse, and Changing with Time Journal March, 2014
A Monte Carlo Synthetic-Acceleration Method for Solving the Thermal Radiation Diffusion Equation Journal February, 2014
