Germina Procop Distinguished R&D Staff Contact PROCOPG@ORNL.GOV All Publications Validation and Testing of ENDF-B-VII Decay Data Validation of ORIGEN for LWR Used Fuel Decay Heat Analysis with SCALE Comparison of Burnup Credit Uncertainty Quantification Methods... PWR ENDF/B-VII Cross-Section Libraries for ORIGEN-ARP... A Statistical Sampling Method for Uncertainty Analysis with SCALE and XSUSA... Impact of Storage Time on the Needed Capture Efficiency for Volatile Radionuclides – 13369 Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Impact of Storage Time on the Needed Capture Efficiency for Volatile Radionuclides – 13369 PWR ENDF/B-VII Cross-Section Libraries for ORIGEN-ARP A Statistical Sampling Method for Uncertainty Analysis with SCALE and XSUSA Validation of new depletion capabilities and ENDF/B-VII data libraries in Scale Design of a Low-Enriched Uranium Fuel for the High Flux Isotope Reactor - Reactor Physics Analyses... Calculation of Heating Values for the High Flux Isotope Reactor PWR Cross Section Libraries for ORIGEN-ARP... Performance and Safety Parameters for the High Flux Isotope Reactor Validation of New Depletion Capabilities and ENDF/B-VII Data Libraries in SCALE An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predictions (NUREG/CR-7108, ORNL/TM-2011/509) Validation of SCALE for High Temperature Gas-Cooled Reactor Analysis (NUREG/CR-7107, ORNL/TM-2011/161) An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predic... Justification for an Increase in Authorized Operating Power at HFIR... Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE... Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE Methodology for Simulating the Irradiation of the Control Elements in HFIR... Development and validation of scale nuclear analysis methods for high temperature gas-cooled reactors... Reference (Axially Graded) Low Enriched Uranium Fuel Design for the High Flux Isotope Reactor (HFIR)... Pagination First page « First Previous page ‹â¶Ä¹ … Page 4 Current page 5 Page 6 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
