Germina Procop Distinguished R&D Staff Contact 865.241.4672 | PROCOPG@ORNL.GOV All Publications Potential Burnup Indicator Identification Based on Power History Decomposition Estimation of Void Fraction History Using Post-irradiation Fuel Isotopics Nuclide Importance to Decay Heat in Advanced Reactors' Spent Fuel Transportation and Storage An introduction to Spent Nuclear Fuel decay heat for Light Water Reactors: a review from the NEA WPNCS Nuclide Inventory Validation: Effect of Nuclear Data Libraries Sister Rod Destructive Examinations (FY23) Appendix D: Fission Gas, Fuel Burnup, and Fuel Isotopic Measurements Assessing criticality implications of porosity misrepresentation in ENDF/B-VIII.1 graphite TSLs and small angle neutron scattering in nuclear graphite DECAY HEAT OF IRRADIATED NUCLEAR FUELS – A STATUS REPORT FROM THE NEA WPNCS... OVERVIEW OF SPENT NUCLEAR FUEL INVENTORY RESULTS FOR THE ARIANE GU3 SAMPLE A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels Editorial: Benchmark experiments, development and needs in support of advanced reactor design Impact of cross section libraries on loading curves for burnup credit criticality safety analysis models... Key Nuclear Data for non-LWR Reactivity Analysis Engagement opportunities in OECD NEA benchmark development Analytical Report for Nuclear Regulatory Commission High Burnup Fuel Specimens New Radiochemical Assay Experiments to Improve the Validation Basis for High Burnup Fuel SCALE 6.2.4 Validation: Reactor Physics Preservation and Characterization of X-10 Graphite Reactor Slugs REGAL International Program: Analysis of experimental data for depletion code validation... Reactor Physics Characteristics of High Flux Isotope Reactor Core Designs with Low-Enriched Uranium Fuels Nuclide Inventory Validation: Radiochemical Assay Data Quality and Modeling Challenges in Benchmark Models Development... Comparison of LWR Decay Heat Calculations Using ANSI/ANS-5.1-2014 Standard and SCALE Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat High Flux Isotope Reactor Low Enriched Uranium U-10Mo Fuel Design Parameters Nuclide Inventory Benchmark for BWR Spent Nuclear Fuel: Challenges in Evaluation of Modeling Data Assumptions and Uncertainties Pagination Current page 1 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
