Georgeta Radulescu Senior R&D Staff Contact 865.241.9998 | RADULESCUG@ORNL.GOV All Publications A Study on the Characteristics of the Radiation Source Terms of Spent Fuel and Various Non-Fuel Hardware for Shielding Applications Determining Fuel Salt Compositions for a Moderated Large-Sized MSR with SCALE... SCALE Shielding Calculations for Advanced Reactor Accident Scenarios Calculation of Extended Subcritical Mass Limits in ANSI/ANS-8.1-2014... SCALE Analyses of Scenarios in the Molten Salt Reactor Fuel Cycle SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario SCALE Demonstration for Sodium-cooled Fast Reactor Fuel Cycle Analysis 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 SCALE 6.2.4 Validation: Radiation Shielding Overview of ORNL SCALE Shielding Analyses for Spent Nuclear Fuel Transportation and Storage Applications... Review of Experimental Data for Validating Computer Codes Used in Shielding Calculations for Spent Fuel Storage and Transportation Systems 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 The Relationship Between Dose Rate and Decay Heat for Spent Nuclear Fuel Casks SAFETY ANALYSIS REPORT FOR PACKAGING SHIELDING & NUCLEAR CRITICALITY SAFETY COURSES DEVELOPED AND CONDUCTED BY OAK RIDGE NATIONAL LABORATORY Overview of the Recent BWR Burnup Credit Project at 91°µÍø Pagination Current page 1 Page 2 Page 3 Next page ›â¶Äº Last page Last » Key Links 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
