Germina Ilas Senior R&D Staff Contact ilasg@ornl.gov | 865.241.4672 All Publications DECAY HEAT OF IRRADIATED NUCLEAR FUELS – A STATUS REPORT FROM THE NEA WPNCS OVERVIEW OF SPENT NUCLEAR FUEL INVENTORY RESULTS FOR THE ARIANE GU3 SAMPLE A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels Editorial: Benchmark experiments, development and needs in support of advanced reactor design... Impact of cross section libraries on loading curves for burnup credit criticality safety analysis models Key Nuclear Data for non-LWR Reactivity Analysis Engagement opportunities in OECD NEA benchmark development Analytical Report for Nuclear Regulatory Commission High Burnup Fuel Specimens... SCALE 6.2.4 Validation: Reactor Physics Preservation and Characterization of X-10 Graphite Reactor Slugs... REGAL International Program: Analysis of experimental data for depletion code validation... Reactor Physics Characteristics of High Flux Isotope Reactor Core Designs with Low-Enriched Uranium Fuels Nuclide Inventory Validation: Radiochemical Assay Data Quality and Modeling Challenges in Benchmark Models Development... Comparison of LWR Decay Heat Calculations Using ANSI/ANS-5.1-2014 Standard and SCALE Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat... High Flux Isotope Reactor Low Enriched Uranium U-10Mo Fuel Design Parameters Nuclide Inventory Benchmark for BWR Spent Nuclear Fuel: Challenges in Evaluation of Modeling Data Assumptions and Uncertainti... Nuclear Data Assessment for Advanced Reactors... LWR DECAY HEAT ANALYSIS WITH SCALE 6.3 AND ENDF/B-VIII.0 NUCLEAR DATA LIBRARIES Modeling of the Molten Salt Reactor Experiment with SCALE Nuclear Data Sensitivity Study for the EBR-II Fast Reactor Benchmark Using SCALE with ENDF/B-VII.1 and ENDF/B-VIII.0 Analysis of PNAR Spent Fuel Safeguards Measurements using the ORIGEN Data Analysis Module... SCALE 6.2.4 Validation for Light Water Reactor Decay Heat Analysis... Validation of SCALE 6.2.4 and ENDF/B-VII.1 data libraries for nuclide inventory analysis in PWR used fuel Reactor Physics Benchmark of the First Criticality in the Molten Salt Reactor Experiment... 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 Modeling and Simulation Development and Deployment Section Nuclear Transmutation and Decay Physics SCALE
