Germina Procop Distinguished R&D Staff Contact PROCOPG@ORNL.GOV All Publications 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... 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... Modeling and simulation of Hanford B reactor experiments... Optimization of Depletion Modeling and Simulation for the High Flux Isotope Reactor 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... 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 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 Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses Validation and Testing of ENDF/B-VII Decay Data Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Pagination First page « First Previous page ‹‹ … Page 3 Current page 4 Page 5 … 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
