William B.J. Marshall Senior R&D Staff Contact marshallwj@ornl.gov | 865.576.7872 All Publications Benchmark Model Temperatures Incorporated into DICE... Estimating Computational Biases for Criticality Safety Applications with Few Neutronically Similar Benchmarks... The Case for and Against a Gadolinium Bias in SCALE: Opening Arguments... ENDF/B-VIII.0 Testing With AMPX and SCALE... A Burnup Credit Approach for Margin Estimation of Loaded Boiling Water Reactor Canisters in UNF-ST&DARDS... Impact of Assembly-Specific Conditions on BWR Burnup Credit... Critical Experiment Design Phase 1 Report for Integral Request 441... Determination of Critical Experiment Correlations for Experiments Involving Arrays of Low-Enriched Fuel Rods... Determination of Critical Experiment Correlations for Experiments Involving High-Enriched Uranium Solutions... Development of Criticality Safety Validation Guidance for NRC-Regulated Activities... Template Engine Applied to Rapid Modeling... As-Loaded Criticality Margin Assessment of Dual Purpose Canisters Using UNF-ST&DARDS... Accuracy and Runtime Improvements with SCALE 6.2... Diagnosing Undersampling Biases in Monte Carlo Eigenvalue and Flux Tally Estimates... Validation for 233U-Fueled Systems in KENO V.a in SCALE 6.2... A Case Study in the Application of TSUNAMI-3D – Part 1, Multigroup... A Case Study in the Application of TSUNAMI-3D – Part 2, Continuous Energy... Study of Axial Burnup Profile Effects on BWR Burnup Credit... Validation of KENO Thermal Moderator Doppler Broadening Method in SCALE 6.2 Beta5 Using Continuous-Energy B-VII.1 Library... Apparent Monte Carlo Source Convergence Problem with BWR Fuel Depleted with Partial Control Blade Insertion... Effect of Control Blade History, and Axial Coolant Density and Burnup Profiles on BWR Burnup Credit... Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit (NUREG/CR-7224, ORNL/TM-2015/544) Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit (NUREG/CR-7224, ORNL/TM-2015/544) Diagnosing Undersampling Biases in Monte Carlo Eigenvalue and Flux Tally Estimates CRITICALITY SAFETY ENHANCEMENTS FOR SCALE 6.2 AND BEYOND... Pagination First page « First Previous page ‹‹ … Page 3 Current page 4 Page 5 … Next page ›› Last page Last » Key Links Curriculum Vitae ORCID 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