GENERAL ASSESSMENT OF CONVECTION HEAT TRANSFER CORRELATIONS FOR MULTIPLE GEOMETRIES AND FLUIDS AT SUPERCRITICAL PRESSURE

被引:3
|
作者
Zahlan, Hussam [1 ]
Leung, Laurence [1 ]
Huang, Yanping [2 ]
Liu, Guangxu [2 ]
机构
[1] Canadian Nucl Labs, Chalk River, ON K0J 1J0, Canada
[2] Nucl Power Inst China, POB 436-72, Chengdu 610213, Sichuan, Peoples R China
关键词
SCWR; supercritical fluid; correlation assessment; water; CO2; tube; rod bundle;
D O I
10.12943/CNR.2017.00003
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 objective of this paper is to assess different correlations independently against a diversified databank-the Canadian Nuclear Laboratories multi-fluid and multi-geometry supercritical heat transfer databank. This databank was recently expanded by adding compiled and original experimental data obtained through collaboration with the Nuclear Power Institute of China. The databank was subjected to screening for outliers, duplicates, and unreliable data. In addition, inappropriate data, not satisfying certain conditions, were removed. Nevertheless, the used databank comprised more than 41 000 measurements of heat transfer to different fluids flowing vertically upward in different geometries. Following a literature review and a compilation of correlations, an assessment of the tabulated correlations was performed against the databank. In total, 24 correlations were considered and applied to the entire database for different fluids including water and different flow geometries including tube, annulus, and rod bundle. Graphical comparison of best-estimate correlations and representative experimental data is presented in this paper. In addition, statistical error analysis was performed and leading correlations were identified. Although the leading correlation showed a standard deviation of less than 6%, variation of predicted wall temperature and heat transfer coefficient with fluid temperature followed the scatter of the experimental data.
引用
收藏
页码:43 / 62
页数:20
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