An Experimental Test Facility to Support Development of the Fluoride Salt Cooled High Temperature Reactor Journal January, 2014
Optimization and Parallelization of the Thermal-Hydraulic Sub-channel Code CTF for High-Fidelity Multi-physics Applications Journal January, 2014
Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response Journal January, 2014
POLARIS: A New Two-Dimensional Lattice Physics Analysis Capability for the SCALE Code System Conference Proceeding January, 2014
Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Journal January, 2014
An Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Transuranic Waste Recycling in Pressurized Water Reactors Journal January, 2014
Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses Journal January, 2014