22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003
Diagram of a thermal-hydraulic test loop model demonstrating conduction in an electrically heated test section. (Courtesy of
Oak Ridge National Laboratories.)
Highlights of this Course
Course Description
Advanced topics emphasizing thermo-fluid dynamic phenomena and analysis methods. Single-heated channel-transient analysis. Multiple-heated channels connected at plena. Loop analysis including single and two-phase natural circulation. Kinematics and dynamics of two-phase flows with energy addition. Boiling, instabilities, and critical conditions. Subchannel analysis. Core thermal analysis approaches.