Germina Procop Distinguished R&D Staff Contact 865.241.4672 | PROCOPG@ORNL.GOV All Publications Application of Depletion Perturbation Theory for Sensitivity Analysis in the High Flux Isotope Reactor Summary: Verification of the ENDF/B-VII.1 and VIII.0 AMPX 1597-group Libraries for Advanced Reactor Analysis Source Range Detector Response Modeling using VERA Overview of the Recent BWR Burnup Credit Project at 91°µÍø 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 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 Optimized Design Performance Analysis Tools for a High Flux Isotope Reactor Low-Enriched Uranium Core... Assessment of SCALE Capabilities for High Temperature Reactor Modeling and Simulation... Neutronic and Thermal-Hydraulic Feasibility Studies for High Flux Isotope Reactor Conversion to Low-Enriched Uranium U3Si2-Al Fuel High Flux Isotope Reactor Low-Enriched Uranium Core Design Optimization Studies Progress Towards a Molten Salt Reactor Experiment Benchmark Evaluation Heat deposition analysis for the High Flux Isotope Reactor’s HEU and LEU core models Design Optimization Studies for a High Flux Isotope Reactor Low-Enriched Uranium Core 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 6.2 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-Fidelity Modeling and Simulation for a High Flux Isotope Reactor Low-Enriched Uranium Core Design Pagination First page « First Previous page ‹â¶Ä¹ … Page 2 Current page 3 Page 4 … Next page ›â¶Äº Last page Last » Key Links 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
