William B.J. Marshall Senior R&D Staff Contact marshallwj@ornl.gov | 865.576.7872 All Publications Cumulative χ2 Metric for VALID for ENDF/B-VII.1 and ENDF/B-VIII.0 in SCALE 6.3b9... Overview of the Tolerance Limit Calculations with Application to TSURFER... Sensitivity Calculations for Systems with Polyethylene Reflector Materials Using CLUTCH 3D Model Visual Verification and Mesh-Based Data Analysis in Fulcrum... Reducing Direct Perturbation Uncertainty for High-Sensitivity Coefficients Discovery of AMPX Thermal Scattering Law Processing Issue for Solid Moderators Analysis of the 30B UF6 Container for Use with Increased Enrichment... Nuclear Data and Cross Section Testing Using ENDF/B-VIII.0 KENO V.a Primer: Performing Calculations using SCALE’s Criticality Safety Analysis Sequence (CSAS5) with Fulcrum... KENO-VI Primer: Performing Calculations using SCALE’s Criticality Safety Analysis Sequence (CSAS6) with Fulcrum... Improved Runtime Performance in KENO-VI Models using Arrays and Holes Initial Efforts Organizing WPNCS SG-8: Preservation of Expert Knowledge and Judgement Applied to Criticality Benchmarks... Selected Uses of TSUNAMI in Critical Experiment Design and Analysis... A Review of TSUNAMI Applications... Updated Primers Generated for SCALE 6.2 for KENO V.a and KENO-VI VADER: A Tool for Criticality Safety Validation S/U Comparison Study with a Focus on USLs Development of SCALE Tools for Sensitivity and Uncertainty Analysis Methodology Implementation (TSUNAMI) from SCALE 5 through SCALE 6.2 Assessment of Critical Experiment Benchmark Applicability to a Large-Capacity HALEU Transportation Package Concept Assessment of Existing Transportation Packages for use with HALEU... SCALE 6.2.4 Validation: Nuclear Criticality Safety MAPPER – A NOVEL CAPABILITY TO SUPPORT NUCLEAR MODEL VALIDATION AND MAPPING OF BIASES AND UNCERTAINTIES... Performing keff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS: Applicable Experiment Selection Description and Use of SCALE Sampler Parametric Capability for Engineering Analysis and Optimization... Performing keff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS: Sensitivity Calculations... Pagination First page « First Previous page ‹‹ Page 1 Current 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