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Thermal Hydraulics in Power Technology

Thermal Hydraulics in Power Technology

As taught in: Spring 2007




Prof. Jacopo Buongiorno

Flames and bubbles surround a thin wire submerged in water.
Burnout of an electrically heated steel wire upon occurrence of the boiling crisis. (Image by Prof. Buongiorno.)

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.

ourse Objective

To understand and model the thermal-hydraulic behavior of key components in nuclear and conventional power systems.

Course Summary

  • Two-phase flow:
    • Conservation equations
    • Flow patterns
    • Void fraction modeling
    • Pressure drop modeling
    • Steam separation
    • Instabilities
    • Critical flow
  • Two-phase heat transfer:
    • Bubble nucleation
    • Pool boiling
    • Subcooled and saturated flow boiling
    • Boiling crises
    • Post-boiling-crisis heat transfer
    • Condensation
  • Thermal design and analysis methodologies:
    • Transient analysis (Single channel)
    • Loop analysis
    • Multiple channel analysis
    • Subchannel analysis
    • Treatment of uncertainties


Amazon logo Collier, J. G., and J. R. Thome. Convective Boiling and Condensation. 3rd ed. New York, NY: Oxford University Press, 1996. ISBN: 9780198562962.

Amazon logo 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.

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