William (B.J.) Marshall Distinguished R&D Staff Contact 865.576.7872 | MARSHALLWJ@ORNL.GOV All Publications Analysis of Axial Coolant Density Profile, Control Blade History, and Axial Burnup Profile on Extended Burnup Credit Monte Carlo Capabilities of the SCALE Code System... Upper Subcritical Limit Calculations with Correlated Integral Experiments Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization... Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization Bias Estimates Used in Lieu of Validation of Fission Products and Minor Actinides in MCNP K<sub>eff</sub> Calculations for PWR Burnup Credit Casks (NUREG/CR-7205, ORNL/TM-2012/544) Bias Estimates Used in Lieu of Validation of Fission Products and Minor Actinides in MCNP K<sub>eff</sub> Calculations for PWR Burnup Credit Casks (NUREG/CR-7205, ORNL/TM-2012/544) Monte Carlo Capabilities of the SCALE Code System CONSEQUENCE ASSESSMENT OF FUEL RECONFIGURATION FOR DRY STORAGE AND TRANSPORTATION PACKAGES... Validation of keff Calculations for Boiling-Water Reactor Fuel at Peak Reactivity in Transportation and Storage Casks Evaluation of Peak Reactivity Analysis of Boiling-Water Reactor Fuel in Transportation and Storage Casks... Mixed Uranium-Plutonium Solution Validation of KENO V.a and KENO-VI in SCALE 6.1.2 and 6.2b3 Using Multigroup and Continuous-Energy ENDF/B-VII.0 Libraries Determination of Experimental Correlations Using the Sampler Sequence Within SCALE 6.2... Additional Studies of the Criticality Safety of Failed Used Nuclear Fuel Special Nuclear Material Inventory Processes at US Domestic Nuclear Power Plants... Applications of nuclear data covariances to criticality safety and spent fuel characterization Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Validation of Criticality Safety Calculations with SCALE 6.2... The SCALE Verified, Archived Library of Inputs and Data - VALID... Consequence Analysis of Spent Nuclear Fuel Reconfiguration Scenarios... Additional Studies of the Criticality Safety of Failed Used Nuclear Fuel Consequences of Used Nuclear Fuel Failure on Criticality Safety... Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Pagination First page « First Previous page ‹‹ … Page 5 Current page 6 Page 7 Next page ›› Last page Last » Key Links Curriculum Vitae Google Scholar ORCID
