Flow through a small break at the bottom of a large pipe with stratified flow

Journal Article · Thu Nov 01 04:00:00 EST 1984 · Nucl. Sci. Eng.; (United States)

OSTI ID:6280418

Reimann, J; Khan, M

A small break in a horizontal coolant pipe is investigated. This flow geometry and accident scenario are of interest in nuclear reactor safety research. For the calculation of break mass flow rate, appropriate experiments are needed, especially for the case where stratified two-phase flow exists in the main pipe. The flow geometry corresponds to a ''T''-junction with a large-diameter ratio of the horizontal pipe, D, to the branch pipe, d. In the present experiments, D was 206 mm, the downward-oriented branch diameters were 6, 12, and 30 mm. Air/water experiments were performed at a system pressure of 0.5 MPa and various differential pressures. The flow field could be observed visually. Photographs reveal both vortex-induced and vortex-free gas pull-through the break and the corresponding correlations for the onset of gas pull-through. The mass flow rate and quality distribution as a function of a dimensionless interface level are presented.

• Research Organization: Kernforschungszentrum, Karlsruhe
• OSTI ID: 6280418
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 88:3; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR-WATER INTERACTIONS
COOLING SYSTEMS
CRACKS
ENERGY SYSTEMS
FLOW RATE
FLUID FLOW
GAS FLOW
GEOMETRY
IMAGES
MATHEMATICS
MEDIUM PRESSURE
PIPES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RESEARCH PROGRAMS
SAFETY
TWO-PHASE FLOW