Georgeta Radulescu Senior R&D Staff Contact radulescug@ornl.gov | 865.241.9998 All Publications Detailed SCALE Dose Rate Evaluations for a Consolidated Interim Spent Nuclear Fuel Storage Facility... Shielding Analysis Capability Of UNF-ST&DARDS... Development of Streamlined Nuclear Safety Analyses for Used Nuclear Fuel Applications... CONTAINMENT ANALYSIS CAPABILITY OF UNF-ST&DARDS... SFCOMPO-2.0: An OECD NEA Database of Spent Nuclear Fuel Isotopic Assays, Reactor Design Specifications, and Operating Data... Design of a Universal Canister System for US High-Level Waste Consolidating Spent Nuclear Fuel Related Data into a Unified Database... Design of a Universal Canister System for U.S. High-Level Waste... UNF-ST&DARDS: A Unique Tool for Automated Characterization of Spent Nuclear Fuel and Related Systems... Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks... A Parametric Analysis of Factors Affecting Calculations of Estimated Dose Rates from Spent Nuclear Fuel Shipments... Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks Shielding Analysis Capability of UNF-ST&DARDS... Evaluation of Simplified Models for Estimating Public Dose from Spent Nuclear Fuel Shipments... Containment Analysis Capability of UNF-ST&DARDS... Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems... A Unified Spent Nuclear Fuel Database and Analysis System... Streamlining Analysis Capabilities for SNF Management... Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses... CONSEQUENCE ASSESSMENT OF FUEL RECONFIGURATION FOR DRY STORAGE AND TRANSPORTATION PACKAGES... Dose Rate Analysis of As-Loaded Spent Nuclear Fuel Casks... SCALE Enhancements for Detailed Cask Dose Rate Analysis... Dose Rate Analysis Capability for Actual Spent Fuel Transportation Cask Contents... Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses Consequence Analysis of Spent Nuclear Fuel Reconfiguration Scenarios... Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Page 3 Next page ›› Last page Last » Key Links ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Data, Criticality Safety, and Radiation Transport Section Radiation Transport Group SCALE