Title of article
Annular flow entrainment rate experiment in a small vertical pipe Original Research Article
Author/Authors
Martin A. Lopez de Bertodano، نويسنده , , Cheng-Shiun Jan، نويسنده , , Stephen G Beus، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 1997
Pages
10
From page
61
To page
70
Abstract
Two-fluid model predictions of film dryout in annular flow, leading to nuclear reactor fuel failure, are limited by the uncertainties in the constitutive relations for the entrainment rate of droplets from the liquid film. The main cause of these uncertainties is the lack of separate-effects experimental data in the range of the operating conditions in nuclear power reactors. An air–water experiment has been performed to measure the entrainment rate in a small pipe. The current data extend the available database in the literature to higher gas and liquid flows and also to higher pressures. The measurements were made with the film extraction technique. A mechanistic model was obtained based on Kelvin–Helmholtzʹ instability theory. The dimensionless model includes the Weber number of the gas and the liquid film Reynolds number. Kataoka and Ishiiʹs correlation (Kataoka, I., Ishii, M., 1982. NUREG/CR-2885, ANL-82-44) is modified based on this model and the new data. The new correlation collapses the present air–water data and Cousins and Hewittʹs data (Cousins, L.B., Hewitt, G.F., 1968. UKAEA Report AERE-R5657) The effects of pressure and surface tension were considered in the derivation so it may be applied for boiling water reactor operating conditions.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
1997
Journal title
Nuclear Engineering and Design Eslah
Record number
888441
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