Germina Ilas Distinguished R&D Staff Contact ilasg@ornl.gov | 865.241.4672 All Publications Neutronic and thermal-hydraulic feasibility studies for High Flux Isotope Reactor conversion to low-enriched uranium silicide... A Metaheuristic Optimization Tool for High Flux Isotope Reactor Low-Enriched Uranium Design... ONRAMP, ORNL Nuclear Resources – Analysis and Modeling Portfolio Assessment of SCALE Capabilities for High Temperature Reactor Modeling and Simulation Optimized Design Performance Analysis Tools for a High Flux Isotope Reactor Low-Enriched Uranium Core High Flux Isotope Reactor Low-Enriched Uranium Core Design Optimization Studies... Neutronic and Thermal-Hydraulic Feasibility Studies for High Flux Isotope Reactor Conversion to Low-Enriched Uranium U3Si2-Al... Progress Towards a Molten Salt Reactor Experiment Benchmark Evaluation... Design Optimization Studies for a High Flux Isotope Reactor Low-Enriched Uranium Core... Heat deposition analysis for the High Flux Isotope Reactor’s HEU and LEU core models... Decay Heat Uncertainty for BWR Used Fuel due to Modeling Data Uncertainties... SFCOMPO-2.0: An OECD NEA Database of Spent Nuclear Fuel Isotopic Assays, Reactor Design Specifications, and Operating Data... High-Fidelity Modeling and Simulation for a High Flux Isotope Reactor Low-Enriched Uranium Core Design... Analysis of New Measurements of Isotopic Compositions in Spent Fuel Samples from Calvert Cliffs Unit 1 Reactor using SCALE 6.... High-Fidelity Modeling and Simulation for a High Flux Isotope Reactor Low-Enriched Uranium Core Design Impact of Reactor Operating Parameters on Cask Reactivity in BWR Burnup Credit... Heat Deposition Analysis for the the High Flux Isotope Reactor's HEU and LEU Core Models Analysis of new measurements of Calvert Cliffs spent fuel samples using SCALE 6.2 Decay Heat Uncertainty for BWR Used Fuel Due to Modeling and Nuclear Data Uncertainties High Flux Isotope Reactor Core Analysis-Challenges and Recent Enhancements in Modeling and Simulation... High-Fidelity Heat Deposition Analysis for the High Flux Isotope Reactor... Re-evaluation of spent nuclear fuel assay data for the Three Mile Island unit 1 reactor and application to code validation High-Fidelity Heat Deposition Analysis for the High Flux Isotope Reactor Re-evaluation of Spent Nuclear Fuel Assay Data for the Three Mile Island Unit 1 Reactor and Application to Code Validation... Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems... Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 … 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