William A Wieselquist SCALE Director Contact wieselquiswa@ornl.gov | 865.574.0204 All Publications Isotopic and Fuel Lattice Parameter Trends in Extended Enrichment and Higher Burnup LWR Fuel Vol II: BWR Fuel... Isotopic and Fuel Lattice Parameter Trends in Extended Enrichment and Higher Burnup LWR Fuel Vol I: PWR fuel... Key Nuclear Data Impacting Reactivity in Advanced Reactors... SCALE Code System... Data-Driven and Precursor-Group Uncertainty Propagation of Lattice Kinetic Parameters in UAM Benchmark... Benchmark Calculations for BEAVRS and Watt Bar Unit 1 Using the SCALE-6.3.0/Polaris-PARCS v3.4.2 Code Package Transition Core Modeling for Extended Enrichment & Accident Tolerant Fuels Using Polaris/PARCS SCALE Modeling of the Sodium Cooled Fast-Spectrum Advanced Burner Test Reactor Benchmark Calculations for Peach Bottom Unit 2 and Hatch Unit 1 Using the SCALE-6.3.0/Polaris-PARCS v3.4.2 Code Package Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety Improvement of SCALE Infrastructure on Microsoft Windows Key Nuclear Data for non-LWR Reactivity Analysis Comparative Analysis of Confidence Metrics for Nuclear Criticality Safety SCALE 6.3.1 User Manual Assessment of Core Physics Characteristics of Extended Enrichment and Higher Burnup LWR Fuels using the Polaris/PARCS Two-Ste... MSR Reactivity, Power, and Inventory Simulations with SCALE... Generalized Bayesian Framework for Evaluation of Integral Benchmark Experiments Uncertainty Quantification of Pebble's Discharge Burnup and Isotopic Inventory using SCALE... Application of SCALE to Molten Salt Fueled Reactor Physics in Support of Severe Accident Analyses... Assessment of SCALE and MELCOR for a generic pebble bed fluoride high-temperature reactor... Cell Dancoff-Based Embedded Self-Shielding Capability for Doubly Heterogeneous Particulate Fuels in SCALE/Polaris... SCALE Modeling of the Fast Spectrum Heat Pipe Reactor... Overview of Recent SCALE Activities for Non-LWR Inventory and Decay Heat Analysis... Rapid Depletion Analysis of Flowing-Pebble Reactor Systems at Equilibrium using SCALE... Initial Development of a Generic Fluoride Salt-Cooled Reactor Model... Pagination Current page 1 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 Modeling and Simulation Development and Deployment Section Nuclear Transmutation and Decay Physics SCALE
