ESTIMATION OF SHEAR-STRESS IN COUNTERCURRENT ANNULAR-FLOW

被引:0
作者
ABE, Y
AKIMOTO, H
MURAO, Y
机构
[1] Department of Nuclear Engineering, Tokai Research Establishment, Japan Atomic Energy Research Institute, Ibaraki-ken, 319-11, Tokai-mura
关键词
2-PHASE FLOW; 2-FLUID MODEL; TRAC-PF1; RELAP5; COUNTERCURRENT FLOW; ANNULAR FLOW; FLOW RATE; VERTICAL PIPE; SHEAR STRESS; FRICTION FACTOR; FLUID MECHANICS;
D O I
10.1080/18811248.1991.9731346
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
The accuracy to which the friction factor is correlated is important in counter-current flow (CCF) analysis using a two-fluid model. Current two-fluid model codes use correlations of friction factors developed for co-current flow, or correlations developed on the assumption of zero wall shear stress. An assessment of two-fluid model codes with these existing correlations shows that the downward flow rate of water is overestimated. An analytical model is developed to calculate the shear stress profile in a liquid film of the CCF in order to obtain information on the shear stress between the interface and the wall. Both this analysis and Bharathan's CCF data show that the wall shear stress acting on the falling water film is approximately of same order as the interfacial shear stress, and the correlation for co-current flow cannot be applied to CCF. Tentative correlations of interfacial and wall friction factors are developed based on the results of the present study.
引用
收藏
页码:208 / 217
页数:10
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