Kevin Robb Group Leader, Energy Systems Development Group, Nuclear Energy and Fuel Cycle Division Contact ROBBKR@ORNL.GOV All Publications Some Hazards and Mitigation Considerations for Molten Halide Salt Experiments Optical and Neutron Imaging Measurements of Gas Bubble Rise Velocity in Molten Salt... Measurement of aerosols in the LSTL and FASTR off-gas systems Development of High Temperature (> 700°C) Molten Salt Pump Technology for Gen3 Solar Power Tower Systems Applications of Flowing Molten Salt Loops with Neutron Irradiation... MOLTEN SALT LOOP OPERATIONAL EXPERIENCE AND TEST CAMPAIGNS IN FY24 Bubble mass transport measurement in the large-scale tests loops at Oak Ridge National Laboratory Density Measurements of Molten LiF–BeF2 and LiF–BeF2–LaF3 Salt Mixtures by Neutron Radiography Design of Instrumentation for Noble Gas Transport in LSTL Needed for Model Development Molten Salt Loop Testing of Sensors and Off-Gas Components - FY23 progress Start-up Operation Experience with a Liquid Fluoride Salt Forced Convection Loop TRACE Analysis of the STS Target Flow Loop Conceptual Design Facility to Alleviate Salt Technology Risks (FASTR): Commissioning Update The effect of interfacial phenomena on gas solubility measurements in molten salts Facility to Alleviate Salt Technology Risks (FASTR): Design Report Density Measurements of Various Molten Sodium, Magnesium, Potassium, and Uranium Chloride Salt Compositions Using Neutron Imaging Engineering-Scale Batch Purification of Ternary MgCl2-KCl-NaCl Salt Using Thermal and Magnesium Contact Treatment Material Selection and Corrosion Studies of Candidate Bearing Materials for Use in Molten Chloride Salt Numerical Investigation of Cartridge Heater Performance Applied to the FASTR Main Heater for Molten Chloride Salts Investigating Thermal Hydraulics Performance of a New Test Section Designed for the LSTL FLiNaK Using CFD Chloride Salt Purification by Reaction With Thionyl Chloride Vapors to Remove Oxygen, Oxygenated Compounds, and Hydroxides Experimental investigation on the coolability of nuclear reactor debris beds using seawater Measuring the solubility of xenon in molten chloride salt... Corrosion of 316H Stainless Steel Specimens in Two FLiBe (LiF-BeF2) Salt Batches Simplified High-Temperature Molten Salt CSP Plant Preconceptual Design Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » Key Links ORCID Google Scholar Profile Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Advanced Reactor Engineering and Development Section Energy Systems Development Group
