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... Sensitivity Analysis of the SCALE/Polaris-PARCS Code Procedure for Watts Bar Unit 1 and Peach Bottom Unit 2 Current Overview of Neutron Moderator Thermal Scattering Kernels for HALEU-Fueled Advanced Reactors Review of Available Critical Experiments and Critical Experiments Facilities to Perform High-Assay Low-Enriched Uranium Fuel ... Dancoff-Based Wigner-Seitz Approximation for the Embedded Self-Shielding Method in SCALE/Polaris SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs SCALE Demonstration for Sodium-cooled Fast Reactor Fuel Cycle Analysis SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario SCALE 6.3.2 User Manual SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems Photonuclear Physics in SCALE Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration Improvement of the SCALE-6.3/XSProc Pointwise Slowing-Down Capability with the Bound Thermal Scattering Data Including High F... Assessment of Core Physics Characteristics of Extended Enrichment and Higher Burnup LWR Fuels using the Polaris/PARCS Two-Step Approach Vol. 2: BWR Fuel 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 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 Improvement of SCALE Infrastructure on Microsoft Windows Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety Key Nuclear Data for non-LWR Reactivity Analysis 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