Georgeta Radulescu Senior R&D Staff Contact radulescug@ornl.gov | 865.241.9998 All Publications A Study on the Characteristics of the Radiation Source Terms of Spent Fuel and Various Non-Fuel Hardware for Shielding Applic... 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 Transport... 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... Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory... SAFETY ANALYSIS REPORT FOR PACKAGING SHIELDING & NUCLEAR CRITICALITY SAFETY COURSES DEVELOPED AND CONDUCTED BY OAK RIDGE NATI... Assessment of Activation on Level L3 of the Tokamak Building due to the ITER Tokamak Cooling Water System... Detailed Radiation Dose Rate Evaluations of Commercial Spent Nuclear Fuel Canisters... MCNP Models for Tokamak Cooling Water System Equipment Evaluations... Dose to Cementitious Material for Moderator Exclusion in a Spent Nuclear Fuel Canister During a Repository Timeframe... Integration of the Full Tokamak Reference Model with the Complex Model for ITER Neutronic Analysis... Detailed SCALE Dose Rate Evaluations for a Consolidated Interim Spent Nuclear Fuel Storage Facility... 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 Data, Criticality Safety, and Radiation Transport Section Radiation Transport Group SCALE
