William (B.J.) Marshall Distinguished R&D Staff Contact 865.576.7872 | MARSHALLWJ@ORNL.GOV All Publications Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems... Monte Carlo Capabilities of the SCALE Code System... Analysis of Axial Coolant Density Profile, Control Blade History, and Axial Burnup Profile on Extended Burnup Credit Upper Subcritical Limit Calculations with Correlated Integral Experiments Monte Carlo Capabilities of the SCALE Code System 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) 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... 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... 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... Additional Studies of the Criticality Safety of Failed Used Nuclear Fuel Consequence Analysis of Spent Nuclear Fuel Reconfiguration Scenarios... Consequences of Used Nuclear Fuel Failure on Criticality Safety... 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
