Alex M Shaw Nuclear Criticality Safety - Research Associate Contact shawam@ornl.gov | 404.547.9916 All Publications Hypothetical Sodium-Cooled Fast Reactor Fuel Transport Using the Existing ES-3100 SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs Scoping Studies on the Impacts of Increased Enrichment on Nuclear Criticality Safety... CRITICALITY SAFETY RECOMMENDATIONS FOR THE TREATMENT OF EXTENDED ENRICHMENT AND HIGH BURNUP FUEL FOR STORAGE AND TRANSPORTATI... IMPACT OF RECENT ENDF NUCLEAR DATA ON BURNUP CREDIT CRITICALITY SAFETY ANALYSES The Case for and Against a Gadolinium Bias in SCALE: Round 2 SCALE Modeling of the Sodium Cooled Fast-Spectrum Advanced Burner Test Reactor Expansion of the ORNL VALID Library Dual Purpose Canister Reactivity and Groundwater Absorption Analyses Analysis of SCALE Criticality and Sensitivity Calculations for Reflected HEU Cylinders... Criticality Safety Implications of Extended-Enrichment and Accident-Tolerant Fuel for Fresh Fuel Storage... Overview of Recent SCALE Activities for Non-LWR Inventory and Decay Heat Analysis SCALE Modeling of the Fast Spectrum Heat Pipe Reactor... Continuous-Energy ENDF/B-VIII.0 Cross Section and SCALE 6.2.4 Performance for Nuclear Criticality Safety Applications: 1H, C,... Impacts of LEU+ and ATF on Fresh Fuel Storage Criticality Safety... Validation of KENO Delayed Neutron Fraction Capabilities... Dual Purpose Canister Reactivity and Groundwater Absorption Analyses Discovery of AMPX Thermal Scattering Law Processing Issue for Solid Moderators Validation of Continuous-Energy ENDF/B-VIII.0 16O, 56Fe, and 63,65Cu Cross Sections for Nuclear Criticality Safety Applications Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Data, Criticality Safety, and Radiation Transport Section Nuclear Criticality Safety Group SCALE
