Donny Hartanto R&D Staff Member - Advanced Nuclear Reactor Analyst Contact hartantod@ornl.gov | 865.341.1843 All Publications SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs SCALE Demonstration for Sodium-cooled Fast Reactor Fuel Cycle Analysis SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems Applications of Thermochemical Modeling in Molten Salt Reactors... Fuel cycle depletion validation and code-to-code verification studies for High Flux Isotope Reactor highly and low-enriched uranium fuel designs Molten Salt Reactor Experiment Simulation using Shift/Griffin SCALE Modeling of the Sodium Cooled Fast-Spectrum Advanced Burner Test Reactor Isotope Production and Materials Irradiation Research Studies to Support HFIR LEU Conversion Assessment... Modeling and Simulation of Fuel Burnup in Pebble Bed Reactors MSR Reactivity, Power, and Inventory Simulations with SCALE... Uncertainty Quantification of Pebble's Discharge Burnup and Isotopic Inventory using SCALE... Application of SCALE to Molten Salt Fueled Reactor Physics in Support of Severe Accident Analyses... Heat Deposition Analysis of Target Materials in the High Flux Isotope Reactor for HEU and LEU Cores Sensitivity and Validation Studies of Plutonium-238 Production with Shift and ORIGEN Current Overview of Neutron Moderator Thermal Scattering Kernels for HALEU-Fueled Advanced Reactors High Flux Isotope Reactor Low-Enriched Uranium Conversion Overview... Griffin's Depletion Calculation of Molten Salt Reactor Experiment... SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario Californium-252 Production Validation Studies at the High Flux Isotope Reactor with Campaign 78 Data Uncertainty Quantification of Fuel Inhomogeneity in Low-enriched Uranium Silicide High Flux Isotope Reactor Design Fuel Conversion Efforts at the High Flux Isotope Reactor – a 2023 Status Update Establishing the Impact of HFIR LEU Conversion through a Comprehensive Set of Reactor Physics Studies... Parameters of Neutron Diffusion Equation for Temperature Effect of MSRE 252Cf Production at the High Flux Isotope Reactor: Nuclear Data Selection and LEU Conversion Impacts Nuclear Data Uncertainty Quantification of High Flux Isotope Reactor Low-Enriched Uranium Design Pagination Current page 1 Page 2 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 Research and Test Reactor Physics Group SCALE
