Validating Mixtures of 233U, 235U, and 239Pu for the Sum-of-Fractions Method Conference Paper July, 2024
DETERMINISTIC-MONTE CARLO HYBRID METHODS FOR EIGENVALUE SENSITIVITY COEFFICIENT CALCULATIONS Conference Paper July, 2024
Effect of Decay Time on Criticality Safety Analyses for High Burnup and Extended Enrichment Fuels Conference Paper July, 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
Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels Journal June, 2024
YIELD CALCULATIONS FOR HO-166m PRODUCTION IN THE HIGH FLUX ISOTOPE REACTOR... ORNL Report April, 2024
Californium-252 Production Validation Studies at the High Flux Isotope Reactor with Campaign 78 Data Conference Paper April, 2024
Scoping Studies on the Impacts of Increased Enrichment on Nuclear Criticality Safety ORNL Report April, 2024
