Donny Hartanto R&D Staff Member - Advanced Nuclear Reactor Analyst Contact 865.341.1843 | HARTANTOD@ORNL.GOV All Publications New Capabilities for Rapid Depletion Analysis of Pebble Bed Reactors in SCALE Consequence analyses of sabotage-induced radiological releases in sodium-cooled fast microreactors... SCALE Analyses of Scenarios in the TRISO-based Heat Pipe Microreactor Fuel Cycle Modeling a Thermal-Spectrum LEU-fueled Molten Salt Reactor Co-fueled with Thorium in SCALE 6.3.1 and Serpent-2 SCALE Modeling and Inventory Generation for a Generic TRISO-Fueled Heat-Pipe Microreactor... Conceptual Design Study of Neutron Detectors for Safeguards Measurement of an Irradiated Pebble Fuel Conversion Efforts at the High Flux Isotope Reactor – a 2025 Status Update Analysis of Asymmetric Control Element Exposure on HFIR Performance Demonstration and Preliminary Validation of Griffin for MSR Depletion with Chemical Removal Parametric Studies... Production of Diagnostic and Therapeutic Radionuclides with Uranium and Thorium Molten Salt Fuel Cycles... HFIR LEU High Density Silicide Dispersion Optimized Design Neutronics Analyses with PHAME... Multigroup Cross Section Generation with the Shift Monte Carlo Code Modeling Continuous Online Refueling with SCALE 6.3.1and Serpent-2 in the EIRENE Novel Molten Salt Reactor Design 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 IDENTIFYING TECHNICAL CHALLENGES IN SAFEGUARDS MEASUREMENTS OF ADVANCED SMALL MODULAR REACTOR FUEL ELEMENTS Comparative Analysis of Heat Deposition Rates and DPA in the HFIR Flux Trap to Support LEU Conversion Application of the Sourdough Fuel Cycle for Rapid Decarbonization of Electric Grids Production of Medically Desirable Radioisotopes in the EIRENE Molten Salt Reactor Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » Key Links ORCID LinkedIn IMPACT@ORNL Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Applications, Methods, and Data Section Reactor and Nuclear Fuel Cycle Analysis Group SCALE
