Validation of CFD models for mono- and polydisperse air-water two-phase flows in pipes

被引：175

作者：

Frank, Th. ^{[1
]}

Zwart, P. J. ^{[2
]}

Krepper, E. ^{[3
]}

Prasser, H. -M. ^{[4
]}

Lucas, D. ^{[3
]}

机构：

[1] ANSYS Germany GmbH, D-83624 Otterfing, Germany

[2] ANSYS Canada Ltd, Waterloo, ON N2L 5Z4, Canada

[3] FZ Dresden Rossendorf FZD, Inst Safety Res, D-01314 Dresden, Germany

[4] Swiss Fed Inst Technol ETHZ, CH-8092 Zurich, Switzerland

来源：

NUCLEAR ENGINEERING AND DESIGN | 2008年 / 238卷 / 03期

关键词：

14;

D O I：

10.1016/j.nucengdes.2007.02.056

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Many flow regimes in nuclear reactor safety (NRS) research and nuclear reactor engineering are characterized by water-steam two-phase flows and require for their accurate CFD simulation the development and validation of appropriate multiphase flow models. This paper is presenting multiphase flow models for the description of mono- and polydisperse bubbly flows in the Eulerian framework of multiphase flow modeling in ANSYS CFX. The models are taking into account interphase momentum transfer due to governing drag and non-drag forces. Furthermore in case of a polydisperse air-water or water-steam bubbly flow the bubble size distribution, bubble break-up and coalescence processes as well as different gas velocities in dependency on the bubble diameter are taken into account in the newly developed inhomogeneous MUSIG model. Both multiphase flow models for mono- and polydisperse bubbly flows have thoroughly been validated and compared to experiments of MT-Loop and TOPFLOW test facilities (FZ Dresden-Rossendorf, Germany). Best practice guidelines (Menter, 2002) have been applied in order to allow for a systematic error quantification and thoroughly assessment of model formulations. (c) 2007 Elsevier B.V. All rights reserved.

引用

页码：647 / 659

页数：13

共 14 条

[1]

*ANSYS INC, 2005, ANSYS CFX 10 US MAN

[2] ANALYSIS OF PHASE DISTRIBUTION IN FULLY-DEVELOPED LAMINAR BUBBLY 2-PHASE FLOW [J].