Germina Procop Distinguished R&D Staff Contact PROCOPG@ORNL.GOV All Publications 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 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 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 Coolant Density and Control Blade History Effects in Extended BWR Burnup Credit... Impact of modeling Choices on Inventory and In-Cask Criticality Calculations for Forsmark3 BWR Spent Fuel... Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems... Optimization of Depletion Modeling and Simulation for the High Flux Isotope Reactor Modeling and simulation of Hanford B reactor experiments... Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization... Extended Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses... Validation of ORIGEN for LWR used fuel decay heat analysis with SCALE Validation and Testing of ENDF/B-VII Decay Data Applications of nuclear data covariances to criticality safety and spent fuel characterization Validation of ORIGEN for LWR Used Fuel Decay Heat Analysis with SCALE Validation and Testing of ENDF/B-VII Decay Data Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Pagination First page « First Previous page ‹â¶Ä¹ … Page 3 Current page 4 Page 5 … 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
