William B.J. Marshall Senior R&D Staff Contact marshallwj@ornl.gov | 865.576.7872 All Publications Current Overview of Neutron Moderator Thermal Scattering Kernels for HALEU-Fueled Advanced Reactors Scoping Studies on the Impacts of Increased Enrichment on Nuclear Criticality Safety... Coupling SCALE with DAKOTA for Axial Burnup Profiles Assessment in Burnup Credit Neutron Absorber Plate Characterization Plan for Criticality Experiments Design IMPACT OF RECENT ENDF NUCLEAR DATA ON BURNUP CREDIT CRITICALITY SAFETY ANALYSES Lost and Found Opportunities Around the Chlorine Worth Study The Case for and Against a Gadolinium Bias in SCALE: Round 2 ASSESSMENT OF EXISTING TRANSPORTATION PACKAGES FOR USE WITH LEU+ AND HALEU MATERIAL Preliminary Design of Critical Experiments Involving Commercially available B4C Neutron Absorber Plates with Low-Enriched UO2 fuel Impact of Thermal Scattering Law on Similarity Assessment in Light-water or Polyethylene-Moderated Systems Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety Engagement opportunities in OECD NEA benchmark development Comparative Analysis of Confidence Metrics for Nuclear Criticality Safety Integral Experiment Request 554 CED-1 Summary Report Generalized Bayesian Framework for Evaluation of Integral Benchmark Experiments... Applicability of ORCEF UF4/CF2 Experiments to Validation of 30-Inch UF6 Cylinders Recent Assessments of Existing Transportation Packages for Use with HALEU Material Expansion of the ORNL VALID Library Performance of the Initial Implementation of the Shift Monte Carlo Code in SCALE 6.3 Multigroup Examination of Nickel-Reflected HEU System Impact of Increased Latent Generations on Sensitivity Calculations with SCALE... Analysis of SCALE Criticality and Sensitivity Calculations for Reflected HEU Cylinders... Revision to SCALE Procedure for Verified, Archived Library of Inputs and Data (VALID) Expanded Validation of Uranium Systems with the KENO Monte Carlo Codes and SCALE 6.2.4... Validation of KENO Delayed Neutron Fraction Capabilities... Pagination Current page 1 Page 2 Page 3 … 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