A new heat transfer correlation and flow regime map for tube bundles

Journal Article · Mon Jan 01 04:00:00 EST 1990 · Journal of Engineering for Gas Turbines and Power; (USA)

DOI:https://doi.org/10.1115/1.2906469· OSTI ID:5505157

Hassan, Y A; Blanchat, T K ^[1]

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1. Texas A and M Univ., College Station, TX (USA). Dept. of Nuclear Engineering

A RELAP5/MOD2 computer code model for a once-through steam generator has been developed. The calculated heat transfer in the nucleate boiling flow was under-predicted as shown by a predicted superheat of only 11{degrees} C( 20{degrees} F), whereas plant range from 22--30{degrees} C (40--60{degrees} F). Existing heat transfer correlations used in thermal-hydraulic computer codes do not provide accurate predictions of the measurement-derived secondary convective heat transfer coefficients for steam generators because they were developed for flow inside tubes, not tube bundles. The RELAP5/MOD2 flow regime map was modified to account for flow across bundles. This modified flow regime map predicts better transition criteria between bubbly-to-slug and slug-to-annular flow. Consequently, improved saturated conditions for the fluid flow at the entrance to the boiler were obtained. A modified Chen-type heat transfer correlation was developed to predict the boiling heat transfer for steam generator tube bundle geometries. This correlation predicts better superheat.

• OSTI ID: 5505157
• Journal Information: Journal of Engineering for Gas Turbines and Power; (USA), Journal Name: Journal of Engineering for Gas Turbines and Power; (USA) Vol. 112:1; ISSN JETPE; ISSN 0742-4795
• Country of Publication: United States
• Language: English

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