Ugur Mertyurek Contact 979.574.6196 | mertyureku@ornl.gov All Publications Assessment of Core Physics Characteristics of Extended Enrichment and Higher Burnup LWR Fuels using the Polaris/PARCS Two-Step Approach Vol. 2: BWR Fuel Assessment of Core Physics Characteristics of Extended Enrichment and Higher Burnup LWR Fuels using the Polaris/PARCS Two-Step Approach. Vol. I: PWR Fuel PCM-based uncertainty reduction in support of model validation for depletion calculations Light Water Reactor LEU+ Lattice Optimization Overview of the Tolerance Limit Calculations with Application to TSURFER MAPPER – A NOVEL CAPABILITY TO SUPPORT NUCLEAR MODEL VALIDATION AND MAPPING OF BIASES AND UNCERTAINTIES Hybrid Reduced Order Modeling for Assembly Calculations Estimation of Void Fraction History Using Post-irradiation Fuel Isotopics Validation of the SCALE/Polaris–PARCS Code Procedure With the ENDF/B-VII.1 AMPX 56-Group Library: Boiling Water Reactor Proceedings for the Workshop on Applied Nuclear Data Activities 2024 Validation of the SCALE/Polaris−PARCS Code Procedure with the ENDF/B-VII.1 AMPX 56-Group Library: Pressurized Water Reactor Benchmark Calculations for Turkey Point Unit 3 and Surry Unit 1 using the SCALE/Polaris--PARCS Procedure Core Physics Characteristics of Extended Enrichment and Higher Burnup Boiling Water Reactor Fuel Enrichment Interpolation for High-Assay Low-Enriched Uranium Fuel Macroscopic Cross Section for Polaris/PARCS Pressurized Water Reactor Gadolinia Pin Location Optimization OVERVIEW OF SPENT NUCLEAR FUEL INVENTORY RESULTS FOR THE ARIANE GU3 SAMPLE Pressurized Water Reactor Gadolinia Pin Location Optimization Benchmark Calculations for BEAVRS and Watt Bar Unit 1 Using the SCALE-6.3.0/Polaris-PARCS v3.4.2 Code Package... Benchmark Calculations for Peach Bottom Unit 2 and Hatch Unit 1 Using the SCALE-6.3.0/Polaris-PARCS v3.4.2 Code Package Transition Core Modeling for Extended Enrichment & Accident Tolerant Fuels Using Polaris/PARCS 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... Pagination Current page 1 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
