Rike Bostelmann R&D Staff – Nuclear Data and Reactor Physics Analyst Contact 865.341.1425 | BOSTELMANNF@ORNL.GOV All Publications New Capabilities for Rapid Depletion Analysis of Pebble Bed Reactors in SCALE Introducing the SLICE Method for Estimating Pebble-Bed Reactor Inventories at Equilibrium Operation with SCALE Demonstration of Monte Carlo Reference Equilibrium Core Solutions for Pebble Bed Reactors Using Shift in kugelpy... SCALE Analyses of Scenarios in the TRISO-based Heat Pipe Microreactor Fuel Cycle SCALE Modeling and Inventory Generation for a Generic TRISO-Fueled Heat-Pipe Microreactor... Porosity in nuclear graphite and its impact on nuclear reactor science and criticality safety applications Multigroup Cross Section Generation with the Shift Monte Carlo Code Development of a Representative Molten Chloride Fast Reactor Model to Assess the Impact of Nuclear Data Nuclear Data Impact on HTR-10 Pebble Bed Reactor Metrics R-matrix analysis of n+natCl reactions up to 1.2 MeV Temperature sensitivity of the equilibrium neutronics and accident analysis of the HTR-10... 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 SCALE Inventory and Reactivity Analysis as Part of the Hermes 2021 PSAR Review SCALE Shielding Calculations for Advanced Reactor Accident Scenarios Modeling Enhancements, Cross-Section Generation Updates, and Benchmarking with Shift SCALE Analyses of Scenarios in the High-Temperature Gas-Cooled Reactor Fuel Cycle SCALE Analyses of Scenarios in the Molten Salt Reactor Fuel Cycle Equilibrium core modeling of a pebble bed reactor similar to the Xe-100 with SCALE SCALE 6.3 Modeling Strategies for Reactivity, Nuclide Inventory, and Decay Heat of Non-LWRs Assessing criticality implications of porosity misrepresentation in ENDF/B-VIII.1 graphite TSLs and small angle neutron scattering in nuclear graphite SCALE 6.3.1 Radiation Source Terms and Shielding Analysis for a Postulated Sodium-Cooled Fast Reactor Accident Scenario SCALE Demonstration for Sodium-cooled Fast Reactor Fuel Cycle Analysis Modeling Enhancements and Benchmarking of Pebble Bed Reactors in the Shift Monte Carlo Code SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems... 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 Applications, Methods, and Data Section Reactor and Nuclear Fuel Cycle Analysis Group SCALE
