Thermal hydraulics in power technology
Master
In Maynard (USA)
Description
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Type
Master
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Location
Maynard (USA)
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Start date
Different dates available
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.
Facilities
Location
Start date
Start date
Reviews
Subjects
- Technology
Course programme
Lectures: 2 sessions / week, 1.5 hours / session
To understand and model the thermal-hydraulic behavior of key components in nuclear and conventional power systems.
Collier, J. G., and J. R. Thome. Convective Boiling and Condensation. 3rd ed. New York, NY: Oxford University Press, 1996. ISBN: 9780198562962.
Todreas, N. E. and M. S. Kazimi. Nuclear Systems. Vol. 2. New York, NY: Francis & Taylor, 1990. ISBN: 9781560320791.
Students may wish to consult other useful references listed in the readings section.
2.006, 10.302, 22.312 or permission of instructor.
Course introduction
Two-phase flow definitions
Conservation equations
Flow patterns
Flow maps
Bubbly flow
Slug flow
Annular flow
Flooding and flow reversal
Mid-term quiz (open book)
All material through Lec #11
Introduction to flow boiling
Onset of nucleate boiling
Multiple heated channels connected at plena
Final exam
Final will cover entire course with specific attention to material of Lec #12-26
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Thermal hydraulics in power technology