William Wieselquist SCALE Director Contact WIESELQUISWA@ORNL.GOV All Publications 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 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 Transport Validation for Advanced Reactor Deployment Dancoff-Based Wigner-Seitz Approximation for the Embedded Self-Shielding Method in SCALE/Polaris Neutronics Study of HTR-10: Impact of Graphite Porosity Representation in ENDF/B-VIII.1 TSLs Benchmark Calculations for Turkey Point Unit 3 and Surry Unit 1 using the SCALE/Polaris--PARCS Procedure Sensitivity Analysis of the SCALE/Polaris-PARCS Code Procedure for Watts Bar Unit 1 and Peach Bottom Unit 2 SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs Assessing criticality implications of porosity misrepresentation in ENDF/B-VIII.1 graphite TSLs and small angle neutron scattering in nuclear graphite SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario Core Physics Characteristics of Extended Enrichment and Higher Burnup Boiling Water Reactor Fuel SCALE Demonstration for Sodium-cooled Fast Reactor Fuel Cycle Analysis SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems... SCALE 6.3.2 User Manual Photonuclear Physics in SCALE Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration FY 2023 Summary Report - Pebble Bed Reactor Domestic Safeguards... 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 Benchmark Calculation for the Watts Bar Unit 1 Cycles 1-3 Using the SCALE 6.3/Polaris–PARCS v3.4.2 Code Package Benchmark Calculation for BEAVRS Cycles 1 and 2 Using the SCALE 6.3/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 Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 … 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
Research Highlight NSITD, RNSD researchers receive Joule Award from NNSA Office of Nonproliferation and Arms Control
