Published 2004 | Version v1
Computer medium

Experiment and analysis of air-water two-phase flow redistribution due to void drift between subchannels for hydrodynamic non-equilibrium flow

  • 1. Kumamoto Univ., Dept. of Mechanical Engineering and Materials Science, Kumamoto (Japan)
  • 2. Mitsubishi Heavy Industries Ltd., Machinery Production Dept., Assembling Section, Hiroshima (Japan)

Description

In order to provide the data to develop a void drift model used in a subchannel analysis, a new experimental data are obtained for air-water two-phase flows in a vertical channel called Ch. M-M, made up of two identical subchannels simplifying a BWR fuel rod bundle. The data include the flow redistribution of both phases due to the void drift and the void fraction in each subchannel under hydrodynamic non-equilibrium flow conditions. By fitting the above data with Lahey et al.'s void settling model (1993), we have determined a void diffusion coefficient in their model. It was found that the void diffusion coefficient for slug, churn and annular flows could be well correlated in terms of a turbulent Peclet number proposed in our previous study (Kawahara and Sadatomi, 2000b). Furthermore, a subchannel analysis code based on a two-fluid model developed in our previous study (Kawahara et al., 2000c) was examined against the present data. In the code, the void settling model was incorporated with usual conservation equations of mass and momentum. From the examination, it was found that the subchannel analysis code can predict well the data on the flow redistribution and the void fraction if appropriate correlations were used to evaluate the wall and the interfacial friction forces needed in the two-fluid model. (author)

Part of:
NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety
Imprint Pagination
3690 p.
Journal Page Range
18 p.

Conference

Title
6. international topical meeting on nuclear reactor thermal hydraulics, operations and safety
Acronym
NUTHOS-6
Dates
4-8 Oct 2004
Place
Nara (Japan)

Optional Information

Notes
This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name THURSDAY October 7, 2004, Paper ID N6P 015.pdf; 37 refs., 16 figs.