Georgeta Radulescu Senior R&D Staff Contact 865.241.9998 | RADULESCUG@ORNL.GOV All Publications SCALE Modeling and Inventory Generation for a Generic TRISO-Fueled Heat-Pipe Microreactor... SCALE Analyses of Scenarios in the TRISO-based Heat Pipe Microreactor Fuel Cycle Advanced Visualization of the Radiation Cast by a Dry Spent Fuel Cask for Public Outreach Determining Fuel Salt Compositions for a Moderated Large-Sized MSR with SCALE Calculation of Extended Subcritical Mass Limits in ANSI/ANS-8.1-2014... SCALE Shielding Calculations for Advanced Reactor Accident Scenarios SCALE Analyses of Scenarios in the Molten Salt Reactor Fuel Cycle SCALE Demonstration for Sodium-cooled Fast Reactor Fuel Cycle Analysis SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario Updated Recommendations Related to Spent Fuel Transport and Dry Storage Shielding Analyses Comprehensive Analysis of Streaming and Shutdown Dose Rate Experiments at JET with ORNL Fusion Neutronics Workflows Review of SCALE Validations Applicable to Spent Nuclear Fuel Shielding Calculations Overview of ORNL SCALE Shielding Analyses for Spent Nuclear Fuel Transportation and Storage Applications... SCALE 6.2.4 Validation: Radiation Shielding Review of Experimental Data for Validating Computer Codes Used in Shielding Calculations for Spent Fuel Storage and Transportation Systems A Study on the Characteristics of the Radiation Source Terms of Spent Fuel and Various Non-Fuel Hardware for Shielding Applications Shutdown Dose Rate Calculations of JET Using ORCS (ORNL R2S Code Suite) Skyshine Calculations for a Large Spent Nuclear Fuel Storage Facility with SCALE 6.2.3 Reactor Cell Neutron Dose for the Molten Salt Breeder Reactor Conceptual Design... UNF-ST&DARDS: A UNIQUE TOOL FOR SPENT NUCLEAR FUEL CHARACTERIZATION AND LONG-TERM FUEL DATABASE MANAGEMENT Fuel Assembly Reference Information for SNF Radiation Source Term Calculations Dose Rate Analysis of the WCS Consolidated Interim Storage Facility Overview of the 2020 SCALE 6.2.4 Validation Report for Radiation Shielding Applications* Demonstration of the On-the-Fly Shielding Analysis Method Best Practices for Shielding Analyses of Activated Metals and Spent Resins from Reactor Operation Pagination Current page 1 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 Applications, Methods, and Data Section Reactor and Nuclear Fuel Cycle Analysis Group SCALE
