Alex Shaw

Alex M Shaw

Research Associate - Nuclear Criticality Safety

Contact

404.547.9916 | 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

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