22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003
Author(s)Todreas, Neil E.
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.
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, Hydraulics, Nuclear energy