Georgeta Radulescu Senior R&D Staff Contact RADULESCUG@ORNL.GOV All Publications Assessment of Activation on Level L3 of the Tokamak Building due to the ITER Tokamak Cooling Water System... 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 Detailed Radiation Dose Rate Evaluations of Commercial Spent Nuclear Fuel Canisters 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 CONTAINMENT ANALYSIS CAPABILITY OF UNF-ST&DARDS Shielding Analysis Capability Of UNF-ST&DARDS Development of Streamlined Nuclear Safety Analyses for Used Nuclear Fuel Applications 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... UNF-ST&DARDS: A Unique Tool for Automated Characterization of Spent Nuclear Fuel and Related Systems... Design of a Universal Canister System for U.S. High-Level Waste 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 Containment Analysis Capability of UNF-ST&DARDS... Shielding Analysis Capability of UNF-ST&DARDS... Evaluation of Simplified Models for Estimating Public Dose from Spent Nuclear Fuel Shipments 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... CONSEQUENCE ASSESSMENT OF FUEL RECONFIGURATION FOR DRY STORAGE AND TRANSPORTATION PACKAGES... Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses... Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current 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
