Design and Assembly of MiniFuel Targets for Characterization of High Burnup UO2 Specimens Irradiated in the High Flux Isotope... ORNL Report June, 2024
Current Overview of Neutron Moderator Thermal Scattering Kernels for HALEU-Fueled Advanced Reactors Conference Paper June, 2024
Review of Available Critical Experiments and Critical Experiments Facilities to Perform High-Assay Low-Enriched Uranium Fuel Transport Validation for Advanced Reactor Deployment Conference Paper June, 2024
Dancoff-Based Wigner-Seitz Approximation for the Embedded Self-Shielding Method in SCALE/Polaris Conference Paper June, 2024
Hypothetical Sodium-Cooled Fast Reactor Fuel Transport Using the Existing ES-3100 ORNL Report May, 2024
SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs ORNL Report May, 2024
Samoa Updater: An Application of the Levenberg-Marquardt Method to Update Delfic Predictions Using Field Measurements ORNL Report May, 2024
SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario Conference Paper April, 2024
Comparison of Temperature-Dependent Cross Section Treatments Within the Shift Monte Carlo Radiation Transport Code ORNL Report April, 2024