Rike Bostelmann R&D Staff – Nuclear Data and Reactor Physics Analyst Contact BOSTELMANNF@ORNL.GOV All Publications 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 Two-step neutronics calculations with Shift and Griffin for advanced reactor systems Assessment of SCALE and MELCOR for a generic pebble bed fluoride high-temperature reactor... 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 Initial Development of a Generic Fluoride Salt-Cooled Reactor Model 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... Methods and Usability Enhancements in Shift for Non-LWR Applications Improvement Of The SCALE-XSPROC Capability For High-Temperature Gas-Cooled Reactor Analysis On the creation of the new ENDF/B-VIII.0 Covariance Library for SCALE Applications with AMPX... Modeling of the Molten Salt Reactor Experiment with SCALE Nuclear Data Sensitivity Study for the EBR-II Fast Reactor Benchmark Using SCALE with ENDF/B-VII.1 and ENDF/B-VIII.0 Thermal Hydraulic Modeling of the Kairos Power Generic Fluoride High Temperature Reactor in MELCOR SCALE Capabilities for High Temperature Gas-Cooled Reactor Analysis Relevant Advanced Reactor Benchmarks for Nuclear Data Assessment Proceedings of the Workshop for Applied Nuclear Data: WANDA 2020 Workshop for Applied Nuclear Data: WANDA2020 Key Nuclear Data Impacting Reactivity in Advanced Reactors... Improvement of SCALE-XSPROC Multigroup Cross Section Processing Based on the CENTRM Pointwise Slowing Down Calculation Reactor simulations with nuclear data uncertainties Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 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 Nuclear Transmutation and Decay Physics SCALE
