Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration ORNL Report December, 2023
On the advantages of radial variation in assembly design for a nuclear reactor core Journal December, 2023
Coupling SCALE with DAKOTA for Axial Burnup Profiles Assessment in Burnup Credit Conference Paper November, 2023
Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 3: Thermal hydraulic evaluation of large break LOCA under high-burnup conditions Journal November, 2023
Uncertainty Quantification of Fuel Inhomogeneity in Low-enriched Uranium Silicide High Flux Isotope Reactor Design ORNL Report November, 2023
Heat and Mass Transfer Coefficients in the Molten Salt Reactor Experiment Conference Paper November, 2023
Parameters of Neutron Diffusion Equation for Temperature Effect of MSRE Conference Paper November, 2023
