William (B.J.) Marshall Distinguished R&D Staff Contact 865.576.7872 | MARSHALLWJ@ORNL.GOV All Publications 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... Neutronic Benchmarking of Small Fast Gas-Cooled Systems SCALE Lattice Physics Code Assessments of Accident Tolerant Fuel Impact of the ENDF/B-VIII.0 Library on Advanced Reactor Simulations Bias Between ENDF/B-VIII and ENDF/B-VII.1 for LEU Pin Array Systems Sensitivity/Uncertainty Comparison Study: Oak Ridge National Laboratory Results ENDF/B-VIII.0 Augmented Covariance Data: The first iteration ASSESSMENT OF NORMALITY FOR CRITICALITY SAFETY BIAS AND BIAS UNCERTAINTY CALCULATION... Criticality Safety Analysis of Spent Nuclear Fuel Canisters Using As-Loaded Configurations THE INFLUENCE OF CHANGES IN NUCLEAR COVARIANCE DATA ON THE CALCULATION OF Ck FOR HIGHLY ENRICHED URANIUM SOLUTION SYSTEMS Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 … Next page ›› Last page Last » Key Links Curriculum Vitae Google Scholar ORCID
