Donny Hartanto R&D Staff Member - Advanced Nuclear Reactor Analyst Contact HARTANTOD@ORNL.GOV All Publications 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 SCALE Demonstration for Sodium-cooled Fast Reactor Fuel Cycle Analysis SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems... Applications of Thermochemical Modeling in Molten Salt Reactors 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
