Jeffrey J Powers Nuclear Reactor and Fuel R&D Staff Contact powersjj@ornl.gov | 865.576.9406 All Publications Modeling the IFR-1 Metallic Fuel Experiment in Bison through the NEAMS Workbench... NEAMS Workbench and Bison Fuel Performance Remote Application Configuration A Review of Molten Salt Reactor Kinetics Models... Neutronic experiments with fluorine rich compounds at LR-0 reactor... DEMONSTRATION OF COUPLED FUEL PERFORMANCE CALCULATIONS IN VERA ON WATTS BAR UNIT 1, CYCLE 1... Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1-3 Progress Towards a Molten Salt Reactor Experiment Benchmark Evaluation... Fuel Cycle Modeling and Simulation of the Molten Salt Breeder Reactor... Fuel Cycle Analysis of Thermal and Fast Spectrum Molten Salt Reactors... Demonstration of Fully Coupled Multiphysics Simulations for Watts Bar Unit 1... Effect of Clad Fast Neutron Flux Distribution on Quarter-Core Fuel Performance Calculations with BISON... Two-Dimensional Neutronic and Fuel Cycle Analysis of the Transatomic Power Molten Salt Reactor... Comparing Sensitivity/Uncertainty Analysis Results for LR-0 Salt Experiments with Salt Reactor Models... Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: motivation and overview... Implementation of Molten Salt Reactor Tools in SCALE... Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview Molten Salt Reactor Neutronics and Fuel Cycle Modeling and Simulation with SCALE Two-Dimensional Neutronic and Fuel Cycle Analysis of the Transatomic Power Molten Salt Reactor (ORNL/TM-2016/742) Transitioning to a Thorium Fuel Cycle with Molten Salt Reactors... ASSESSING PELLET-CLAD INTERACTION WITH VERA: WBN1, CYCLES 6–7... Analysis of Operational and Safety Performance for Candidate Accident Tolerant Fuel and Cladding Concepts... VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12... Modeling and Simulation of the Start-Up of a Thorium-Based Molten Salt Reactor... A Fully Ceramic Microencapsulated Fuel for Space Reactor Applications... Analysis of Key Safety Metrics of Thorium Utilization in LWRs... Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Page 3 … Next page ›› Last page Last » Key Links ORCID