Visual Experimental Study on Boiling Crisis Induced by Flow Oscillation in a Single Rod Channel

Liu Haidong; Chen Deqi; Qin Jiang; Liu Hanzhou; Yan Peigang; Liu Wei

doi:10.13832/j.jnpe.2022.01.0035

Volume 43 Issue 1

Feb. 2022

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2022 > 43(1): 35-41

Liu Haidong, Chen Deqi, Qin Jiang, Liu Hanzhou, Yan Peigang, Liu Wei. Visual Experimental Study on Boiling Crisis Induced by Flow Oscillation in a Single Rod Channel[J]. Nuclear Power Engineering, 2022, 43(1): 35-41. doi: 10.13832/j.jnpe.2022.01.0035

Citation:

Liu Haidong, Chen Deqi, Qin Jiang, Liu Hanzhou, Yan Peigang, Liu Wei. Visual Experimental Study on Boiling Crisis Induced by Flow Oscillation in a Single Rod Channel[J]. Nuclear Power Engineering, 2022, 43(1): 35-41. doi: 10.13832/j.jnpe.2022.01.0035

Citation:

PDF( 20938 KB)

Visual Experimental Study on Boiling Crisis Induced by Flow Oscillation in a Single Rod Channel

doi: 10.13832/j.jnpe.2022.01.0035

1.
Key Laboratory of Aerospace Thermophysics, Ministry of Industry and Information Technology, School of Energy Science and Engineering, Harbin Institute of Technology, Harbin, 150001, China
2.
Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Chongqing University, Ministry of Education, Chongqing, 400044, China
3.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2020-12-07
Rev Recd Date: 2021-01-18
Publish Date: 2022-02-01

Abstract

Abstract

In order to deeply analyze the influence characteristics of boiling crisis induced by boiling two-phase flow oscillation, this paper takes deionized water as the working medium, a single rod channel with a cross section of 19 mm×19 mm and an outer diameter of 9.5 mm at the center as the research object. Through visual experimental research on boiling two-phase flow characteristics under different thermal parameters, combined with the behavior of bubbles and vapor-liquid interface characteristics, the influence characteristics of boiling crisis induced by flow oscillations are analyzed. The results show that flow oscillation is easy to occur at low pressure, low mass flow rate and low inlet subcooling, which leads to the early occurrence of boiling crisis, and the critical heat flux is significantly lower than that under stable conditions; With the increase of wall heat flux, the two-phase flow patterns in the channel appear bubble flow, slug flow, combined slug flow, stirred flow, violent stirred flow and unstable annular flow; When the flow oscillates violently, there is reflux in the channel; When the boiling crisis occurs, the pressure drop fluctuation in the channel is the largest, and the corresponding flow pattern is unstable annular flow. Therefore, the flow oscillation in the single rod channel may lead to the early occurrence of boiling crisis.
- Visual experiment,
- Two-phase flow,
- Flow oscillation,
- Bubble,
- Boiling crisis

FullText(HTML)

References(29)

References

[1]	徐济鋆. 沸腾传热和气液两相流[M]. 北京: 中国原子能出版社, 1993: 273-307.
[2]	杨世铭, 陶文铨. 传热学[M]. 第四版, 北京: 高等教育出版社, 2006: 205-227.
[3]	李昊翔,彭传新,昝元锋. 水平圆管临界热流密度实验研究[J]. 核动力工程,2018, 39(1): 43-46.
[4]	李权,焦拥军,于俊崇. 竖直加热圆管内过冷沸腾及CHF数值模拟[J]. 核动力工程,2015, 36(1): 168-172.
[5]	刘伟,彭诗念,江光明,等. 高压工况下管内垂直向上流动沸腾CHF机理模型研究[J]. 核动力工程,2018, 39(6): 172-177.
[6]	吴鸽平. 环形窄缝通道内流动沸腾临界热流密度和含汽率的研究[D]. 西安: 西安交通大学, 2003.
[7]	李勇,熊万玉,闫晓,等. 不同流道间隙下矩形通道临界热流密度的实验研究[J]. 核动力工程,2012, 33(3): 42-45. doi: 10.3969/j.issn.0258-0926.2012.03.009
[8]	卢冬华,黄彦平,白雪松. 高流速下窄矩形通道内临界热流密度试验研究[J]. 核动力工程,2004, 25(2): 118-122. doi: 10.3969/j.issn.0258-0926.2004.02.006
[9]	赵大卫,刘文兴,熊万玉,等. 双面均匀加热矩形窄缝通道内DNB型临界热流密度理论预测[J]. 核动力工程,2016, 37(3): 21-25.
[10]	TONG L S. Boundary-layer analysis of the flow boiling crisis[J]. International Journal of Heat and Mass Transfer, 1968, 11(7): 1208-1210,IN5,1211. doi: 10.1016/0017-9310(68)90037-9
[11]	WEISMAN J, PEI B S. Prediction of critical heat flux in flow boiling at low qualities[J]. International Journal of Heat and Mass Transfer, 1983, 26(10): 1463-1477. doi: 10.1016/S0017-9310(83)80047-7
[12]	LEE C H, MUDAWWAR I. A mechanistic critical heat flux model for subcooled flow boiling based on local bulk flow conditions[J]. International Journal of Multiphase Flow, 1988, 14(6): 711-728. doi: 10.1016/0301-9322(88)90070-5
[13]	GALLOWAY J E, MUDAWAR I. CHF mechanism in flow boiling from a short heated wall—II. Theoretical CHF model[J]. International Journal of Heat and Mass Transfer, 1993, 36(10): 2527-2540. doi: 10.1016/S0017-9310(05)80191-7
[14]	LIU W, NARIAI H. Viewpoint of subcooled flow boiling critical heat flux mechanism[J]. Chemical Engineering & Technology, 2002, 25(4): 447-453.
[15]	LE CORRE J M. Flow regimes and mechanistic modeling of critical heat flux under subcooled flow boiling conditions[D]. Pittsburgh: Carnegie Mellon University, 2007.
[16]	王艳林,周磊,昝元锋,等. 并联多通道流动不稳定性实验研究[J]. 核动力工程,2021, 42(1): 15-17.
[17]	BOURE J A, BERGLES A E, TONG L S. Review of two-phase flow instability[J]. Nuclear Engineering and Design, 1973, 25(2): 165-192. doi: 10.1016/0029-5493(73)90043-5
[18]	MISHIMA K, NISHIHARA H. The effect of flow direction and magnitude on CHF for low pressure water in thin rectangular channels[J]. Nuclear Engineering and Design, 1985, 86(2): 165-181. doi: 10.1016/0029-5493(85)90221-3
[19]	GHIONE A, NOEL B, VINAI P, et al. Criteria for onset of flow instability in heated vertical narrow rectangular channels at low pressure: an assessment study[J]. International Journal of Heat and Mass Transfer, 2017, 105: 464-478. doi: 10.1016/j.ijheatmasstransfer.2016.10.012
[20]	陆祺,周铃岚,沈才芬,等. 流动不稳定性对沸腾临界触发机制的实验研究[J]. 工程热物理学报,2020, 41(4): 966-975.
[21]	LOWDERMILK W H, LANZO C D, SIEGEL B L. Investigation of boiling burnout and flow stability for water flowing in tubes[J]. Technical Report Archive & Image Library, 1958, 9(5): 357-368.
[22]	BERGLES A E, LOPINA R F, FIORI M P. Critical-heat-flux and flow-pattern observations for low-pressure water flowing in tubes[J]. Journal of Heat Transfer, 1967, 89(1): 69-74. doi: 10.1115/1.3614324
[23]	QU W L, MUDAWAR I. Measurement and correlation of critical heat flux in two-phase micro-channel heat sinks[J]. International Journal of Heat and Mass Transfer, 2004, 47(10-11): 2045-2059. doi: 10.1016/j.ijheatmasstransfer.2003.12.006
[24]	QU W L, MUDAWAR I. Measurement and prediction of pressure drop in two-phase micro-channel heat sinks[J]. International Journal of Heat and Mass Transfer, 2003, 46(15): 2737-2753. doi: 10.1016/S0017-9310(03)00044-9
[25]	LEE J, JO D, CHAE H, et al. The characteristics of premature and stable critical heat flux for downward flow boiling at low pressure in a narrow rectangular channel[J]. Experimental Thermal and Fluid Science, 2015, 69: 86-98. doi: 10.1016/j.expthermflusci.2015.07.015
[26]	唐瑜,陈炳德,熊万玉,等. 高压条件下矩形并联双通道流动不稳定与沸腾临界现象分布区域的实验研究[J]. 核动力工程,2016, 37(2): 60-64.
[27]	何海沙. 矩形窄通道内PM-CHF特性实验研究[D]. 哈尔滨: 哈尔滨工程大学, 2019.
[28]	刘伟,彭诗念,江光明,等. 高压工况下圆管内垂直向上流动沸腾CHF关系式比较研究[J]. 核动力工程,2019, 40(1): 152-155.
[29]	MOFFAT R J. Describing the uncertainties in experimental results[J]. Experimental Thermal and Fluid Science, 1988, 1(1): 3-17. doi: 10.1016/0894-1777(88)90043-X