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Nuclear Reactor Thermal Hydraulics

 A wide variety of nuclear reactor thermal hydraulic problems have been investigated at Oregon State University. These include the development of a library of best estimate thermal hydraulic computer codes for nuclear reactor safety analysis, experimental studies of the mixing of reactor fluids in reactor relevant geometries, experimental studies to characterize a variety of two-phase flow patterns, the analysis of countercurrent flooding behavior in reactor geometries, the analysis of condensation induced water hammers, and a study of the effects of fluid particle interactions on interfacial transfer and flow structure. OSU’s ongoing research is instrumental in the design and licensing of new reactors. 

For more information contact Professor Qiao Wu.