Experimental analysis of heat transfer characteristics out of single C-shaped tube under subcooled boiling conditions

被引:0
|
作者
Liu Y.-B. [1 ]
Wang X.-S. [1 ]
Wang H. [1 ]
Chen Q.-Z. [1 ]
Meng X.-Y. [1 ]
机构
[1] Key Laboratory of Pressure Systems and Safety, Ministry of Education, East China University of Science & Technology, Shanghai
关键词
Bubbles; Experimental validation; Heat transfer; Subcooled boiling; Visualization;
D O I
10.3969/j.issn.1003-9015.2021.00.005
中图分类号
学科分类号
摘要
In order to explore heat transfer characteristics out of passive residual heat removal heat exchanger (PRHR HX) tubes, which affects operation safety of nuclear reactors, a single C-shaped tube setup was built and experimental study was conducted with visualization technology. The results show that with the increase of nucleation number and bubble size, the water temperatures at horizontal and vertical observation points increase from 95.1 and 84.7 ℃ to saturation temperature, respectively. Correspondingly, the heat transfer coefficients increase in the range of 7 930.9-14 545.9 W∙m-2∙℃-1 and 2 876.9-8 742.2 W∙m-2∙℃-1, and the subcooling degrees decrease from 4.9 and 15.3 ℃ to nearly 0 ℃. The wall temperature and superheat degree vary within 2.0 ℃. The differences between experimental heat fluxes and predicted values with empirical correlations based on the q-Δθsatn and superposition model were obvious. Empirical correlations were fitted for horizontal and vertical sections based on the weakening coefficient model under subcooled boiling conditions, and the average prediction errors were 1.9% and 6.4%, respectively. Horizontal section under saturation boiling conditions was also fitted and the error was within ±5%. © 2022, Editorial Board of "Journal of Chemical Engineering of Chinese Universities". All right reserved.
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页码:346 / 353
页数:7
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