Alex Shaw Nuclear Criticality Safety - Research Associate Contact SHAWAM@ORNL.GOV All Publications Bias and Bias Uncertainty for High Burnup and Extended Enrichment Fuels in Criticality Safety Analyses Validation Studies Burnup Credit Loading Curves for High-Burnup and Extended Enrichment Fuels Post-closure Criticality Control Optimization Scheme for RCCAs in As-Loaded Dual Purpose Canisters Considering Site Specific ... Conducting MUSiC Modeling Studies Effect of Decay Time on Criticality Safety Analyses for High Burnup and Extended Enrichment Fuels ASSESSMENT OF VALIDATION FOR BURNUP CREDIT CALCULATIONS FOR LEU+ AND HIGH BURNUP FUEL Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels Investigating a Potential Hafnium Bias in SCALE 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 TRANSPORTATION SYSTEMS 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, 58,60Ni, 182,183,184,186W, 235,238U, 239Pu 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 Pagination Current page 1 Page 2 Next page ›â¶Äº Last page Last » 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
