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22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2005

Diagram of a thermal-hydraulic test loop model.
Diagram of a thermal-hydraulic test loop model demonstrating conduction in an electrically heated test section. (Image courtesy of Oak Ridge National Laboratory.)

Highlights of this Course

This course features assignments and exams, both with solutions.

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."

 

Staff

Instructor:
Prof. Jacopo Buongiorno

Course Meeting Times

Lectures:
Two sessions / week
1.5 hours / session

Level

Graduate

Additional Features

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Translations
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