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.
To understand and model the thermal-hydraulic behavior of key components in nuclear and conventional power systems.
Void fraction modeling
Pressure drop modeling
Two-phase heat transfer:
Subcooled and saturated flow boiling
Post-boiling-crisis heat transfer
Thermal design and analysis methodologies:
Transient analysis (Single channel)
Multiple channel analysis
Treatment of uncertainties
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.