Georgeta Radulescu Senior R&D Staff Contact RADULESCUG@ORNL.GOV All Publications SCALE Enhancements for Detailed Cask Dose Rate Analysis Dose Rate Analysis of As-Loaded Spent Nuclear Fuel Casks... 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... ADVANTG Shielding Analysis for Closure Operations in an Open-Mode Repository Considerations for an Integrated Storage, Transportation, and Disposal Canister Integrating Data and Analysis Capabilities for Cask-Specific Safety Evaluations Validation of new depletion capabilities and ENDF/B-VII data libraries in Scale An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predictions (NUREG/CR-7108, ORNL/TM-2011/509) Validation of New Depletion Capabilities and ENDF/B-VII Data Libraries in SCALE An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predic... Radiation Transport Evaluations for Repository Science Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE... REVIEW OF RESULTS FOR THE OECD/NEA PHASE VII BENCHMARK: STUDY OF SPENT FUEL COMPOSITIONS FOR LONG−TERM DISPOSAL... Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions (ORNL/TM-2010/44) Evaluation of PWR Isotopic Composition Data... SCALE Validation Experience Using an Expanded Isotopic Assay Database for Spent Nuclear Fuel Enhancements to the Burnup Credit Criticality Safety Analysis Sequence in SCALE... SENSITIVITY AND UNCERTAINTY ANALYSIS OF COMMERCIAL REACTOR CRITICALS FOR BURNUP CREDIT... Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit (NUREG/CR-6951, ORNL/TM-2006/87) Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Page 2 Current page 3 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
