Ugur Mertyurek Contact mertyureku@ornl.gov | 979.574.6196 All Publications Nuclide Inventory Benchmark for BWR Spent Nuclear Fuel: Challenges in Evaluation of Modeling Data Assumptions and Uncertainti... Non-intrusive Alternative to Generalized Linear Least-Squares Methodology for Criticality Safety Applications... Estimation of Recoverable Energies in Neutron-Induced Fission and Capture with Associated Uncertainties... Isotopic and Fuel Lattice Parameter Trends in Extended Enrichment and Higher Burnup LWR Fuel Vol II: BWR Fuel... Lattice physics calculations using the embedded self-shielding method in polaris, Part II: Benchmark assessment... Lattice Physics Calculations Using the Embedded Self-Shielding Method in Polaris, Part I: Methods and Implementation MAPPER – A NOVEL CAPABILITY TO SUPPORT NUCLEAR MODEL VALIDATION AND MAPPING OF BIASES AND UNCERTAINTIES... Verification of the sensitivity and uncertainty-based criticality safety validation techniques: ORNL’s SCALE case study... SCALE Lattice Physics Code Assessments of Accident Tolerant Fuel Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory Initial Application of TSUNAMI for Validation of Advanced Fuel Systems Preliminary TSUNAMI Assessment of the Impact of Accident Tolerant Fuel Concepts on Reactor Physics Validation... Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit... SCALE 6.2 REACTOR PHYSICS CODE ACCURACY ASSESMENT FOR LIGHT WATER REACTOR FUEL... BWR Geometry Enhancements for the Polaris Lattice Physics Code... Accuracy and Runtime Improvements with SCALE 6.2... Automatic Coarse Energy Group Structure Optimization by Minimizing Reaction Rate Differences for the SCALE and CASL Code Syst... POLARIS: A New Two-Dimensional Lattice Physics Analysis Capability for the SCALE Code System Dimensionality Reduction Algorithms for Big Nuclear Data Streams with Application to SCALE Microscopic Cross Sections... Development of ORIGEN Libraries for Mixed Oxide (MOX) Fuel Assembly Designs... Development of ORIGEN libraries for mixed oxide (MOX) fuel assembly designs CRITICALITY SAFETY ENHANCEMENTS FOR SCALE 6.2 AND BEYOND... Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems... Hybrid Reduced Order Modeling for Assembly Calculations... MODERNIZATION STRATEGIES FOR SCALE 6.2... Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Page 3 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