Experimental Evaluation of Two-Phase Heat Transfer Coefficient Under Oscillatory Flow Conditions and Correlation Development

被引：0

作者：

Kumar, Rakesh ^{[1
,2
]}

Chandraker, Dinesh K. ^{[1
,2
]}

Dasgupta, Arnab ^{[1
,2
]}

Nayak, Arun K. ^{[1
,2
]}

机构：

[1] Homi Bhabha Natl Inst, Mumbai 400094, Maharashtra, India

[2] Bhabha Atom Res Ctr, Reactor Engn Div, Mumbai 400085, Maharashtra, India

来源：

JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE | 2023年 / 9卷 / 01期

关键词：

oscillatory flow; heat transfer coefficient; correction factor; empirical correlation; NARROW ANNULAR DUCT; BUBBLE CHARACTERISTICS; VERTICAL TUBES; FLUX; PRESSURE; R-134A; CHF;

D O I：

10.1115/1.4055090

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：

Natural circulation boiling water reactors (NCBWRs) are prone to flow instabilities. Due to instabilities, heat transfer deteriorates. However, the extent to which the heat transfer coefficient (HTC) deteriorates is not well established. In this work, experiments are conducted under controlled flow oscillations to evaluate the impact of the time period, mean mass flux, and amplitude ratio on HTC. Existing correlations for HTC are compared with experimental results and are found to be not satisfactory. To improve the predictions of HTC, correction factors (CFs) are proposed for existing correlations. Further, an improved HTC correlation has been developed, incorporating new nondimensional numbers.

引用

页数：10

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