William (B.J.) Marshall Distinguished R&D Staff Contact MARSHALLWJ@ORNL.GOV All Publications Integral Experiment Request 554: CED-2 Summary Report Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles Quantifying the Impact of Isotopically Dependent Fuel TSLs on LCT Systems in VALID Investigating Hydrogen Thermal Scattering Law Data with Critical Benchmarks Burnup Credit Loading Curves for High-Burnup and Extended Enrichment Fuels Bias and Bias Uncertainty for High Burnup and Extended Enrichment Fuels in Criticality Safety Analyses Validation Studies Conducting MUSiC Modeling Studies Validating Mixtures of 233U, 235U, and 239Pu for the Sum-of-Fractions Method Effect of Decay Time on Criticality Safety Analyses for High Burnup and Extended Enrichment Fuels ASSESSMENT OF VALIDATION FOR BURNUP CREDIT CALCULATIONS FOR LEU+ AND HIGH BURNUP FUEL Impact of Light Water Covariance on Integral Benchmarks Investigating Similarity Differences for Light-Water-Moderated and Polyethylene-Moderated Systems DETERMINISTIC-MONTE CARLO HYBRID METHODS FOR EIGENVALUE SENSITIVITY COEFFICIENT CALCULATIONS Current Overview of Neutron Moderator Thermal Scattering Kernels for HALEU-Fueled Advanced Reactors Investigating a Potential Hafnium Bias in SCALE Review of Available Critical Experiments and Critical Experiments Facilities to Perform High-Assay Low-Enriched Uranium Fuel Transport Validation for Advanced Reactor Deployment Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels Scoping Studies on the Impacts of Increased Enrichment on Nuclear Criticality Safety Neutron Absorber Plate Characterization Plan for Criticality Experiments Design Coupling SCALE with DAKOTA for Axial Burnup Profiles Assessment in Burnup Credit Lost and Found Opportunities Around the Chlorine Worth Study The Case for and Against a Gadolinium Bias in SCALE: Round 2 IMPACT OF RECENT ENDF NUCLEAR DATA ON BURNUP CREDIT CRITICALITY SAFETY ANALYSES 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 Pagination Current page 1 Page 2 Page 3 … Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae
