Thermal Hydraulics in Power Technology

As taught in: Spring 2007

Level:

Graduate

Instructors:

Prof. Jacopo Buongiorno

Course Features

Course Description

Technical Requirements

Burnout of an electrically heated steel wire upon occurrence of the boiling crisis. (Image by Prof. Buongiorno.)

Course Features

• Assignments (no solutions)
• Exams and 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.

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

Texts

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.