22.313 Thermal Hydraulics in Power Technology
Emphasis on thermo-fluid dynamic phenomena and analysis methods for conventional and nuclear power stations. 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. Subchannel analysis.
22.313 will be offered this semester (Spring 2017). It is instructed by E. Baglietto.
Lecture occurs 1:00 PM to 2:30 PM on Tuesdays and Thursdays in 24-121.
This class counts for a total of 12 credits.
You can find more information at the DSpace@MIT: 22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003 site.
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