William Wieselquist SCALE Director Contact 865.574.0204 | WIESELQUISWA@ORNL.GOV All Publications Modeling of the Molten Salt Reactor Experiment with SCALE On the creation of the new ENDF/B-VIII.0 Covariance Library for SCALE Applications with AMPX... Nuclear Data Sensitivity Study for the EBR-II Fast Reactor Benchmark Using SCALE with ENDF/B-VII.1 and ENDF/B-VIII.0 Neutronic Characteristics of ENDF/B-VIII.0 Compared to ENDF/B-VII.1 for Light-Water Reactor Analysis Assessment of ORIGEN Reactor Library Development for Pebble-Bed Reactors Based on the PBMR-400 Benchmark Reactivity Underestimation of ENDF/B-VIII.0 Compared with ENDF/B-VII.1 for the Pressurized Water Reactor Depletion Analysis Thermal Hydraulic Modeling of the Kairos Power Generic Fluoride High Temperature Reactor in MELCOR Overview of the 2020 SCALE 6.2.4 Validation Report for Radiation Shielding Applications* Hierarchical Data Format for Nuclear Data Sensitivities Estimation of Recoverable Energies in Neutron-Induced Fission and Capture with Associated Uncertainties Extended Enrichment Accident Tolerant LWR Fuel Isotopic and Lattice Parameter Trends Lattice Physics Calculations Using the Embedded Self-Shielding Method in Polaris, Part I: Methods and Implementation VADER: A Tool for Criticality Safety Validation Initial Efforts Organizing WPNCS SG-8: Preservation of Expert Knowledge and Judgement Applied to Criticality Benchmarks Development of SCALE Tools for Sensitivity and Uncertainty Analysis Methodology Implementation (TSUNAMI) from SCALE 5 through SCALE 6.2 SCALE Capabilities for High Temperature Gas-Cooled Reactor Analysis (alpha,n) nuclear data scoping study... Relevant Advanced Reactor Benchmarks for Nuclear Data Assessment Nuclear Data Scoping Studies for Nonproliferation - paper Modeling and Simulation of Oxygen Transport in High Burnup LWR Fuel SCALE 6.3.0 User Manual Modeling Molten Salt Reactor Fission Product Removal with SCALE... Improvement of SCALE-XSPROC Multigroup Cross Section Processing Based on the CENTRM Pointwise Slowing Down Calculation Recent SCALE Activities within the Nuclear Criticality Safety Program The MAVRIC-Shift Sequence in SCALE for Radiation Transport and Shielding Calculations with Automated Variance Reduction and Parallel Computing Pagination First page « First Previous page ‹â¶Ä¹ … Page 3 Current page 4 Page 5 … Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae 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
