William Wieselquist SCALE Director Contact WIESELQUISWA@ORNL.GOV All Publications 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 Key Nuclear Data for non-LWR Reactivity Analysis Comparative Analysis of Confidence Metrics for Nuclear Criticality Safety SCALE 6.3.1 User Manual MSR Reactivity, Power, and Inventory Simulations with SCALE Assessment of Core Physics Characteristics of Extended Enrichment and Higher Burnup LWR Fuels using the Polaris/PARCS Two-Step Approach. Vol. I: PWR Fuel Application of SCALE to Molten Salt Fueled Reactor Physics in Support of Severe Accident Analyses... Generalized Bayesian Framework for Evaluation of Integral Benchmark Experiments... Uncertainty Quantification of Pebble's Discharge Burnup and Isotopic Inventory using SCALE 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 Initial Development of a Generic Fluoride Salt-Cooled Reactor Model Comparison of LWR Decay Heat Calculations Using ANSI/ANS-5.1-2014 Standard and SCALE 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 SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis Extension of SCALE/Sampler’s Sensitivity Analysis... Revisit of the Dancoff-Based Wigner-Seitz Approximation for Pointwise and Multigroup Resonance Self-Shielding Calculations in SCALE Nuclear Data Assessment for Advanced Reactors... Characteristic Solutions for Advection Problems with Isotopic Evolution with SCALE/ORIGEN Improvement Of The SCALE-XSPROC Capability For High-Temperature Gas-Cooled Reactor Analysis Solving Advection Problems with Isotopic Evolution with SCALE/ORIGEN Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 … 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
