22.313[J] Thermal Hydraulics in Power Technology


Class Info

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.

This class has 2.006, 10.302, and 22.312 as prerequisites.

22.313[J] will not be offered this semester. It will be instructed by E. Baglietto.

This class counts for a total of 12 credits. This is a graduate-level class.

In the Spring 2014 Subject Evaluations, 22.313[J] was rated 5.9 out of 7.0. You can find more information at the DSpace@MIT: 22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003 site.

MIT 22.313[J] Thermal Hydraulics in Power Technology Related Textbooks
MIT 22.313[J] Thermal Hydraulics in Power Technology On The Web
DSpace@MIT: 22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003
Tags
two-phase single-heated analysis channel-transient

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