Diagram of a thermal-hydraulic test loop model demonstrating conduction in an electrically heated test section. (Image courtesy of
Oak Ridge National Laboratory.)
Course Highlights
Course Description
This course covers the thermo-fluid dynamic phenomena and analysis methods for conventional and nuclear power stations. Specific topics include: kinematics and dynamics of two-phase flows; steam separation; boiling, instabilities, and critical conditions; single-channel transient analysis; multiple channels connected at plena; loop analysis including single and two-phase natural circulation; and subchannel analysis.
Starting in Spring 2007, this course will be offered jointly in the Departments of Nuclear Science and Engineering, Mechanical Engineering, and Chemical Engineering, and will be titled "Thermal Hydraulics in Power Technology."
*Some translations represent previous versions of courses.