EXPERIMENTAL STUDIES OF SPACER GRID THERMAL HYDRAULICS IN THE DISPERSED FLOW FILM BOILING REGIME

被引:10
|
作者
Riley, M. P. [1 ]
Mohanta, L. [1 ]
Cheung, F. B. [1 ]
Bajorek, S. M. [2 ]
Tien, K. [2 ]
Hoxie, C. L. [2 ]
机构
[1] Penn State Univ, Dept Mech & Nucl Engn, University Pk, PA 16802 USA
[2] US Nucl Regulatory Commiss, Off Nucl Regulatory Res, Washington, DC 20555 USA
关键词
reflood; dispersed flow film boiling; wet spacer grid; HEAT-TRANSFER; TUBES;
D O I
10.13182/NT14-80
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
Spacer grids have been found to enhance downstream convective heat transfer and to strongly influence droplet size distributions through early spacer grid rewet and droplet breakup. Existing models for enhancement of heat transfer and droplet breakup, however, do not appear to accurately account for these interactions between the coolant and the spacer grid. Data from two series of rod bundle heat transfer tests, low injection rate forced reflood tests, and droplet injection tests are presented in this paper to describe the effects of the spacer grids during dispersed flow film boiling. Heat transfer downstream of the spacer grids is clearly enhanced by the presence of the droplets, while the downstream droplet size was found to depend on the condition of the spacer grid: dry or wetted. Results of this study demonstrate the need to adequately account for the separate modes of dry and wet spacer grid heat transfer enhancement in predicting the thermal-hydraulic behavior during reflood transients.
引用
收藏
页码:336 / 344
页数:9
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