SCALE Workshops

NRC/ORNL Technical Workshop on “Fuel Cycle Impacts of HBU-EE and HALEU Fuel Designs,”August 12-13, 2026

• Germina Procop and Rabab Elzohery,“NUREG/CR-7303: Validating Actinides and Fission Products for Burnup Credit Criticality Safety Analyses – Nuclide Compositions Prediction with Extended Validation Basis”

• Georgeta Radulescu and Alex Shaw,“NUREG/CR-7306: Fuel Assembly and Irradiation Parametric Study for Extended-Enrichment and High-Burnup Light-Water Reactor Spent Nuclear Fuel in Dry Storage Casks and Transportation Packages”

• Travis Greene, Mathieu Dupont and Alex Shaw,“NUREG/CR-7308: Sensitivity / Uncertainty Methods for Nuclear Criticality Safety Validation”

• Mathieu Dupont, Alex Shaw and Lisa Fassino,“NUREG/CR-7309: Validation Studies for High Burnup and Extended Enrichment Fuels in Burnup Credit Criticality Safety Analyses”

• Alex Shaw, Travis Greene and Mathieu Dupont,“NUREG/CR-7311: Determination of Bias and Bias Uncertainty for Criticality Safety Computational Methods”

• Yves Robert, Georgeta Radulescu, Lisa Fassino and Alex Shaw,“NUREG/CR-XXXX: Nuclide Importance to Criticality Safety, Decay Heat, and Radiation Shielding Analyses for Transport and Storage of Non-LWR Fuel”

SCALE Nuclide Inventory and Radiation Shielding for Spent Fuel Storage and Transportation, U.S. Nuclear Regulatory Commission Professional Development Center, Rockville, Maryland, September 29-October 2, 2025.

• Presented by Cihangir Celik, Lisa Fassino, and Steve Skutnik

Spent Fuel Pool and New Fuel Vault Criticality Safety Analyses with SCALE Training, U.S. Nuclear Regulatory Commission Headquarters, Rockville, Maryland, June 9-13, 2025.

• Presented by Ugur Mertyurek, Alex Shaw, and Will Wieselquist.

EPRI ATF/LEU+/HBU Workshop – Review of Technical Readiness for Fresh and Spent Fuel Storage (Wet and Dry) & Transportation, Washington, DC, February 11-13, 2025.

• Will Wieselquist, “Overview of SCALE Capabilities and Technical Evaluation for Readiness for HALEU/HBU/ATF.”

• Arzu Alpan, “Fuel Assembly and Irradiation Parametric Study for Extended-Enrichment and High-Burnup LWR Spent Nuclear Fuel in Dry Storage Casks and Transportation Packages (NUREG/CR 7306).”

• Ugur Mertyurek and Walid Metwally, “Sensitivity Uncertainty Methods for Criticality Safety Validation.”

• Germina Procop, “NUREG/CR 7303 – Validating Actinides and Fission Products for Burnup Credit Criticality Safety Analyses –Nuclide Compositions Prediction with Extended Validation Basis.”

• Walid Metwally, Mathieu Dupont, Alex Lang, Veronica Karriem, B. J.. Marshall, Cihangir Celik, Lisa Fassino, and Alex Shaw, “Validation Studies for High Burnup and Extended Enrichment Fuels in Burnup Credit Criticality Safety Analyses.”

• Kang Seog Kim, BK Jeon, Andy Ward, Ugur Mertyurek, Matthew Jessee, Rabab Elzohery, Will Wieselquist, “Polaris/PARCS Validation.”

International Conference on Physics of Reactors (PHYSOR 2024), San Francisco, California, April 21-24, 2024.

• Rike Bostelmann, Travis Greene, Germina Procop, Ugur Mertyurek, and Will Wieselquist, ”Validation with SCALE: How to Connect Paper Reactors with Reality.”