Contact Information quallsal@ornl.gov 865.803.8631 orcid.org/0000-0002-6094-7779 Related Organizations Fusion and Fission Energy and Science Directorate National Center for Computational Sciences Oak Ridge Leadership Computing Facility Technology Integration Group A L Qualls Reactor Technology Integration Lead All Publications Recent progress in shattered pellet injection technology in support of the ITER disruption mitigation system*... NUCLEAR POWER CONCEPTS FOR HIGH-POWER ELECTRIC PROPULSION MISSIONS TO MARS... Early Phase Molten Salt Reactor Safety Evaluation Considerations... Characterization of nuclear graphite for molten salt reactors (MSR)... Dynamic System Models for Informing Licensing and Safeguards Investigations of Molten Salt Reactors – Revision 1... Demonstration of the Advanced Dynamic System Modeling Tool TRANSFORM in a Molten Salt Reactor Application via a Model of the ... Advanced Reactor Technology Program Molten Salt Reactor Campaign FY 2018 Summary... Molten Salt Reactors and Associated Safeguards Challenges and Opportunities... Development, Fabrication, and Testing of a Prototype High Temperature Fission Chamber... A Summary of the Department of Energy's Advanced Demonstration and Test Reactor Options Study... Dynamic Radioisotope Power System Development for Space Explorations... Steps in the Development of Nuclear Thermal Propulsion Fuels... Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: core design and safety ana... Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: motivation and overview... Preconceptual design of a fluoride high termperature salt-cooled engineering demonstration reactor: Motivation and overview Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis Dynamic Radioisotope Power System Development for Space Explorations Thermal-Hydraulic Design of a Fluoride High-Temperature Demonstration Reactor... Core Design Characteristics of the Fluoride Salt-Cooled High Temperature Demonstration Reactor... Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview Extrusion Development of Graphite-Based Composite Fuel for Nuclear Thermal Propulsion... Coating Development on Graphite-Based Composite Fuel for Nuclear Thermal Propulsion... Performance of a Thermally Stable Polyaromatic Hydrocarbon in a Simulated Concentrating Solar Power Loop ... Recapturing Graphite-Based Fuel Element Technology for Nuclear Thermal Propulsion... Mixtures of SF6 – CO2 as working fluids for geothermal power plants ... Pagination Current page 1 Page 2 Next page ›› Last page Last »
