Ugur Mertyurek Contact MERTYUREKU@ORNL.GOV All Publications Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety Comparative Analysis of Confidence Metrics for Nuclear Criticality Safety SCALE 6.2.4 Validation: Reactor Physics Generalized Bayesian Framework for Evaluation of Integral Benchmark Experiments... REGAL International Program: Analysis of experimental data for depletion code validation... Transition Core Modeling for Extended Enriched, Accident Tolerant Fuel Using PARCS/Polaris Comparison of LWR Decay Heat Calculations Using ANSI/ANS-5.1-2014 Standard and SCALE Overview of Recent SCALE Activities for Non-LWR Inventory and Decay Heat Analysis LEU+ BWR Lattice Design Optimization of Using SCALE/Polaris Nuclide Inventory Benchmark for BWR Spent Nuclear Fuel: Challenges in Evaluation of Modeling Data Assumptions and Uncertainties 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 I: Methods and Implementation Lattice physics calculations using the embedded self-shielding method in polaris, Part II: Benchmark assessment 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 Initial Application of TSUNAMI for Validation of Advanced Fuel Systems Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory 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 Automatic Coarse Energy Group Structure Optimization by Minimizing Reaction Rate Differences for the SCALE and CASL Code Syst... Accuracy and Runtime Improvements with 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
