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ISSN Online: 2377-424X

ISBN Print: 978-1-56700-474-8

ISBN Online: 978-1-56700-473-1

International Heat Transfer Conference 16
August, 10-15, 2018, Beijing, China

MEASUREMENT OF LOCAL PARAMETERS OF TWO-PHASE FLOW IN TUBE BUNDLE

Get access (open in a dialog) DOI: 10.1615/IHTC16.mpf.023716
pages 6821-6830

Abstract

Detailed knowledge on two-phase flow characteristics inside tube bundle is essential for properly design steam generators in nuclear power plants or other shell and tube heat exchangers Adiabatic two-phase experiments were carried out by using simulant fluids in a reduced scaled facility of U-bend section. Physical parameters such as void fraction and velocity along U-bend tubes were obtained, and visualization of two-phase flow was conducted.
In addition to the U-bend experiment, short-span tube bundle experiment was carried out in order to visualize two-phase flow passing through tube bundles. In both of the U-bend experiment and the short-span bundle experiment, BOPs (Bi-optical probes) are installed for measuring local void fraction and gas-liquid interfacial velocity. BOP sensor can distinguish liquid phase from gas phase by the difference in refractive indices of two phases. By detecting the delay of the signal between two probes, BOP sensor can measure the interfacial velocity between gas and liquid phases.
The data sets obtained in the U-bend and short-span experiments are planned to be utilized as validation data for simulation code and the same simulation code can be applied to other shell and tube heat exchangers.