Rike Bostelmann R&D Staff – Nuclear Data and Reactor Physics Analyst Contact 865.341.1425 | bostelmannf@ornl.gov All Publications 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 SCALE Demonstration for Sodium-cooled Fast Reactor Fuel Cycle Analysis Modeling Enhancements and Benchmarking of Pebble Bed Reactors in the Shift Monte Carlo Code 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 depletion capabilities for molten salt reactors and other liquid-fueled systems Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration Modeling Enhancements and Demonstration of Shift Capabilities for PBR and MSR Equilibrium Cycle Modeling of a Generic mHTGR Similar to the Xe-100 SCALE Modeling of the Sodium Cooled Fast-Spectrum Advanced Burner Test Reactor Key Nuclear Data for non-LWR Reactivity Analysis MSR Reactivity, Power, and Inventory Simulations with SCALE... Application of SCALE to Molten Salt Fueled Reactor Physics in Support of Severe Accident Analyses... Modeling, Performance Assessment, and Nodal Data Analysis of TRISO-Fueled Systems with Shift Assessment of SCALE and MELCOR for a generic pebble bed fluoride high-temperature reactor... Two-step neutronics calculations with Shift and Griffin for advanced reactor systems... Initial Development of a Generic Fluoride Salt-Cooled Reactor Model SCALE Modeling of the Fast Spectrum Heat Pipe Reactor... Rapid Depletion Analysis of Flowing-Pebble Reactor Systems at Equilibrium using SCALE... Overview of Recent SCALE Activities for Non-LWR Inventory and Decay Heat Analysis Objectives and Status of Neutronics Sub-Exercises of the OECD/NEA Benchmark for Uncertainty Analysis in Modelling for Design, Operation and Safety Analysis of SFRs SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis Extension of SCALE/Sampler’s Sensitivity Analysis... Nuclear Data Assessment for Advanced Reactors... 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 Modeling and Simulation Development and Deployment Section Nuclear Transmutation and Decay Physics SCALE
