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ISSN Online: 2377-424X

ISBN Print: 0-89116-559-2

International Heat Transfer Conference 8
August, 17-22, 1986, San Francisco, USA

STEAM-WATER CRITICAL FLOW THROUGH SMALL PIPES FROM STRATIFIED UPSTREAM REGIONS

Get access (open in a dialog) DOI: 10.1615/IHTC8.4660
pages 2307-2311

要約

Discharge of fluid through a small pipe connected to a large horizontal pipe containing stratified fluid is of concern in reactor safety evaluations. This paper presents the results of an experimental investigation into the levels associated with incipient vapor pull-through and liquid entrainment for branches oriented at the top, side and bottom of the horizontal pipe and into the steam quality entering the break after the onset of entrainment of the second phase. The main pipe was 102 mm in diameter and the break tubes were 4, 6, and 10 mm in diameter and 123 mm in length. Both air-water and steam-water were used at pressures up to 1.07 MPa. Incipient data, together with data from other studies, are correlated in terms of Froude number, Bond number and viscosity number for submerged breaks and in terms of Froude number alone for liquid entrainment. Quality correlations are presented and discussed in the context of the critical flow calculation for a small break LOCA.