Donny Hartanto R&D Staff Member - Advanced Nuclear Reactor Analyst Contact HARTANTOD@ORNL.GOV All Publications New Capabilities for Rapid Depletion Analysis of Pebble Bed Reactors in SCALE... SCALE Analyses of Scenarios in the TRISO-based Heat Pipe Microreactor Fuel Cycle... HFIR LEU High Density Silicide Dispersion Optimized Design Neutronics Analyses with PHAME Multigroup Cross Section Generation with the Shift Monte Carlo Code... R-matrix analysis of n+natCl reactions up to 1.2 MeV Consequence Analyses of Sabotage-Induced Radiological Releases in Sodium-Cooled Fast Microreactors Californium-252 production at the High Flux Isotope Reactor - II: Comparison between the highly enriched uranium and a proposed low-enriched uranium core Californium-252 production at the High Flux Isotope Reactor − I: Validation study using campaign data Determining Fuel Salt Compositions for a Moderated Large-Sized MSR with SCALE SCALE Analyses for Inventory and Reactivity Analysis as Part of the Hermes 2021 PSAR Review Plutonium-238 Production Sensitivity and Validation Studies Continued: Effects of Core Component Compositions... SCALE Shielding Calculations for Advanced Reactor Accident Scenarios Comparative Analysis of Heat Deposition Rates and DPA in the HFIR Flux Trap to Support LEU Conversion Sensitivity Studies on Fuel Burnup and Plutonium Buildup in Pebble Bed Reactors for Fuel Parameter Perturbations SCALE Inventory and Reactivity Analysis as Part of the Hermes 2021 PSAR Review SCALE Analyses of Scenarios in the High-Temperature Gas-Cooled Reactor Fuel Cycle SCALE Analyses of Scenarios in the Molten Salt Reactor Fuel Cycle Modeling Enhancements, Cross-Section Generation Updates, and Benchmarking with Shift 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 Heat Deposition Analysis of Target Materials in the High Flux Isotope Reactor for HEU and LEU Cores SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs Californium-252 Production Validation Studies at the High Flux Isotope Reactor with Campaign 78 Data High Flux Isotope Reactor Low-Enriched Uranium Conversion Overview Griffin's Depletion Calculation of Molten Salt Reactor Experiment Pagination Current page 1 Page 2 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 Research and Test Reactor Physics Group SCALE
