Germina Procop Distinguished R&D Staff Contact 865.241.4672 | PROCOPG@ORNL.GOV All Publications Nuclear Data Assessment for Advanced Reactors... LWR DECAY HEAT ANALYSIS WITH SCALE 6.3 AND ENDF/B-VIII.0 NUCLEAR DATA LIBRARIES Modeling of the Molten Salt Reactor Experiment with SCALE Nuclear Data Sensitivity Study for the EBR-II Fast Reactor Benchmark Using SCALE with ENDF/B-VII.1 and ENDF/B-VIII.0 Analysis of PNAR Spent Fuel Safeguards Measurements using the ORIGEN Data Analysis Module... SCALE 6.2.4 Validation for Light Water Reactor Decay Heat Analysis... Validation of SCALE 6.2.4 and ENDF/B-VII.1 data libraries for nuclide inventory analysis in PWR used fuel Reactor Physics Benchmark of the First Criticality in the Molten Salt Reactor Experiment... 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 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 SCALE Capabilities for High Temperature Gas-Cooled Reactor Analysis Secondary-Source Core Reload Modeling with VERA 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 Assessments Relevant Advanced Reactor Benchmarks for Nuclear Data Assessment SFCOMPO Database of Spent Nuclear Fuel Assay Data – the Next Frontier Key Nuclear Data Impacting Reactivity in Advanced Reactors... Validation of ORIGEN for VVER-440 Spent Fuel with Application to Fork Detector Safeguards Measurements Conceptual Fuel Element Design Candidates for Conversion of High Flux Isotope Reactor with Low-Enriched Uranium Silicide Dispersion Fuel Automated Fuel Design Optimization for High Flux Isotope Reactor Low Enriched Uranium Core Design Metaheuristic Optimization Tool Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 … 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
