William Wieselquist SCALE Director Contact WIESELQUISWA@ORNL.GOV All Publications Development of Decay Heat Sensitivity Analysis Capability in SCALE/ORIGEN Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety 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 Polaris-PARCS Sensitivity Study on LWR Fuel Cycles: Polaris Input Options Core Physics Characteristics of Extended Enrichment and High Burnup Boiling Water Reactor Fuel Benchmark Calculation for Surry Unit 1 Cycles 1-3 Using the SCALE 6.3/Polaris–PARCS v3.4.2 Code Package... Benchmark Calculation for the Peach Bottom Unit 2 Cycles 1-3 Using the SCALE 6.3/Polaris–PARCS v3.4.2 Code Package... Benchmark Calculation for the Quad Cities Unit 1 Cycles 1-3 Using the SCALE 6.3/Polaris–PARCS v3.4.2 Code Package Determining Fuel Salt Compositions for a Moderated Large-Sized MSR with SCALE Benchmark Calculation for Turkey Point Unit 3 Cycles 1-3 Using the SCALE 6.3/Polaris–PARCS v3.4.2 Code Package Benchmark Calculation for the Hatch Unit 1 Cycles 1-3 Using the SCALE 6.3/Polaris–PARCS v3.4.2 Code Package SCALE Analyses for Inventory and Reactivity Analysis as Part of the Hermes 2021 PSAR Review SCALE Inventory and Reactivity Analysis as Part of the Hermes 2021 PSAR Review SCALE Shielding Calculations for Advanced Reactor Accident Scenarios Error Propagation Analysis, from LWR Assemblies to Plants, Using SCALE/Polaris-PARCS with the ENDF/B-VII.1 and VIII.0 AMPX 56... Towards an Energy Deposition Tally in SCALE/MAVRIC Development of the ENDF/B-VII.1 and VIII.0 AMPX 61- and 258-Group Libraries for SCALE 7.0/Polaris LWR Analysis SCALE Analyses of Scenarios in the High-Temperature Gas-Cooled Reactor Fuel Cycle SCALE Analyses of Scenarios in the Molten Salt Reactor Fuel Cycle Validation of the SCALE/Polaris–PARCS Code Procedure With the ENDF/B-VII.1 AMPX 56-Group Library: Boiling Water Reactor Validation of the SCALE/Polaris−PARCS Code Procedure with the ENDF/B-VII.1 AMPX 56-Group Library: Pressurized Water Reactor 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
Research Highlight NSITD, RNSD researchers receive Joule Award from NNSA Office of Nonproliferation and Arms Control
