Published December 1997 | Version v1
Journal article

Annular flow entrainment rate experiment in a small vertical pipe

  • 1. Purdue Univ., Lafayette, IN (United States). School of Nuclear Engineering
  • 2. Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, West Mifflin, PA 15122-0079 (United States)

Description

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-Helmholtz' instability theory. The dimensionless model includes the Weber number of the gas and the liquid film Reynolds number. Kataoka and Ishii's correlation (Kataoka, I., Ishii, M., (1982)) is modified based on this model and the new data. The new correlation collapses the present air-water data and Cousins and Hewitt's data (Cousins, L.B. (1968)) The effects of pressure and surface tension were considered in the derivation so it may be applied for boiling water reactor operating conditions. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
178
Journal Issue
1
Journal Page Range
p. 61-70.
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Notes
12 refs.