Germina Ilas Distinguished R&D Staff Contact ilasg@ornl.gov | 865.241.4672 All Publications High Flux Isotope Reactor Low Enriched Uranium Low Density Silicide Fuel Design Parameters Analysis with the ORIGEN Module of PNAR Spent Fuel Measurements for Nuclear Safeguards Applications SCALE Capabilities for High Temperature Gas-Cooled Reactor Analysis Secondary-Source Core Reload Modeling with VERA Sister Rod Destructive Examinations (FY20) Appendix D, Fission Gas Analysis, Fuel Rod Burnup and Isotopic Measurements... Preliminary Benchmark Calculations of Spent Nuclear Fuel Isotopic Compositions Using BWR Assay Data... Neutronic and Thermal-Hydraulic Design Studies for High Flux Isotope Reactor Conversion to Low-Enriched Uranium High Density ... Fuel Conversion Efforts at the High Flux Isotope Reactor – a 2020 Status Update... Status Update on the High Precision Isotopic Measurements on High Burnup LWR Fuel in 2020 Modeling and Simulation of a High Flux Isotope Reactor Representative Core Model for Updated Performance and Safety Basis Ass... Relevant Advanced Reactor Benchmarks for Nuclear Data Assessment SFCOMPO Database of Spent Nuclear Fuel Assay Data – the Next Frontier Validation of ORIGEN for VVER-440 Spent Fuel with Application to Fork Detector Safeguards Measurements Key Nuclear Data Impacting Reactivity in Advanced Reactors... Metaheuristic Optimization Tool Conceptual Fuel Element Design Candidates for Conversion of High Flux Isotope Reactor with Low-Enriched Uranium Silicide Disp... Automated Fuel Design Optimization for High Flux Isotope Reactor Low Enriched Uranium Core Design Application of Depletion Perturbation Theory for Sensitivity Analysis in the High Flux Isotope Reactor Source Range Detector Response Modeling using VERA Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory Summary: Verification of the ENDF/B-VII.1 and VIII.0 AMPX 1597-group Libraries for Advanced Reactor Analysis... A Metaheuristic Optimization Tool for High Flux Isotope Reactor Low-Enriched Uranium Core Design... Verification of the ENDF/B-VII.1 and VIII.0 AMPX 1597-Group Libraries for Advanced Reactor Analysis... Design optimization methods for high-performance research reactor core design Review of Experimental Assay Data for PWR Spent Fuel... Pagination First page « First Previous page ‹‹ Page 1 Current 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
