
Burnout of an electrically heated steel wire upon occurrence of the boiling crisis. (Image courtesy of Prof. Buongiorno.)
Instructor(s)
Prof. Jacopo Buongiorno
MIT Course Number
22.313J / 2.59J / 10.536J
As Taught In
Spring 2007
Level
Graduate
Course Description
Course Features
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.
Other Versions
Other OCW Versions
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