Current Overview of Neutron Moderator Thermal Scattering Kernels for HALEU-Fueled Advanced Reactors Conference Paper June, 2024
Dancoff-Based Wigner-Seitz Approximation for the Embedded Self-Shielding Method in SCALE/Polaris 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
Neutronics Study of HTR-10: Impact of Graphite Porosity Representation in ENDF/B-VIII.1 TSLs Conference Paper June, 2024
Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels Journal June, 2024
Impact of Increased Monte Carlo Parameters on Sensitivity Calculations with SCALE... Conference Paper June, 2024
Design and Assembly of MiniFuel Targets for Characterization of High Burnup UO2 Specimens Irradiated in the High Flux Isotope Reactor ORNL Report 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
