22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2005
Author(s)Buongiorno, Jacopo, 1971-
Thermal Hydraulics in Nuclear Power Technology
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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. From the course home page: 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."
reactor, nuclear reactor, thermal behavior, hydraulic, hydraulic behavior, heat, modeling, steam, stability, instability, thermo-fluid dynamic phenomena, single-heated channel-transient analysis, Multiple-heated channels, Loop analysis, single and two-phase natural circulation, Kinematics, two-phase flows, subchannel analysis, Core thermal analysis