William (B.J.) Marshall Distinguished R&D Staff Contact 865.576.7872 | MARSHALLWJ@ORNL.GOV All Publications 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 Addressing Fission Product Validation in MCNP Burnup Credit Criticality Calculations... Impact of modeling Choices on Inventory and In-Cask Criticality Calculations for Forsmark3 BWR Spent Fuel... Upper Subcritical Calculations Based on Correlated Data... Coolant Density and Control Blade History Effects in Extended BWR Burnup Credit... Validation of SCALE 6.2 Criticality Calculations Using KENO V.A and KENO-VI Investigation of the Continuous-Energy Sensitivity Methods in SCALE 6.2 Using TSUNAMI-3D Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems... Development and Testing of Neutron Cross Section Covariance Data for SCALE 6.2... Determination of Critical Experiment Correlations Using the Sampler Sequence Within SCALE 6.2... Pagination First page « First Previous page ‹‹ … Page 4 Current page 5 Page 6 … Next page ›› Last page Last » Key Links Curriculum Vitae Google Scholar ORCID
