Published February 2009 | Version v1
Journal article

An investigation on heat transfer characteristics of different pressure steam-water in vertical upward tube

  • 1. State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, Shaanxi 710049 (China)

Description

Within the range of pressure from 9 to 30 MPa, mass velocity from 600 to 1200 kg/(m2 s), and heat flux at inner wall from 200 to 600 kW/m2, experiments have been performed to investigate the heat transfer characteristics of steam-water two-phase flow in vertical upward tube. The outer diameter of the tube is 32 mm, and the wall thickness is 3 mm. Based on results, it was found that Dryout is the main mechanism of the heat transfer deterioration in the sub-critical pressure region. Near the critical pressure, when the heat transfer deterioration occurs, the steam quality of water is lower than that in the sub-critical pressure region, so that DNB is the main mechanism in this pressure region. At supercritical pressure, the heat transfer performance in circular channel is improved and enhanced. Heat transfer deterioration phenomenon is observed when the fluid bulk temperature approaches to the pseudo-critical value. Nusselt correlation of the forced-convection heat transfer in supercritical pressure region has been provided, which can be used to predict heat transfer coefficient of the vertical upward flow in tube

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2008.10.026

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2008.10.026;
PII
S0029-5493(08)00542-6;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
239
Journal Issue
2
Journal Page Range
p. 381-388
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.