Experimental Study on Gas-Liquid Counter Current Flow Limitation in Inclined Pipes

Ma Youfu; Han Linfeng; Wen Huiming; Lyu Junfu; Wang Shuo

doi:10.13832/j.jnpe.2024.03.0051

Volume 45 Issue 3

Jun. 2024

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Ma Youfu, Han Linfeng, Wen Huiming, Lyu Junfu, Wang Shuo. Experimental Study on Gas-Liquid Counter Current Flow Limitation in Inclined Pipes[J]. Nuclear Power Engineering, 2024, 45(3): 51-59. doi: 10.13832/j.jnpe.2024.03.0051

Citation:

Ma Youfu, Han Linfeng, Wen Huiming, Lyu Junfu, Wang Shuo. Experimental Study on Gas-Liquid Counter Current Flow Limitation in Inclined Pipes[J]. Nuclear Power Engineering, 2024, 45(3): 51-59. doi: 10.13832/j.jnpe.2024.03.0051

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Experimental Study on Gas-Liquid Counter Current Flow Limitation in Inclined Pipes

doi: 10.13832/j.jnpe.2024.03.0051

Ma Youfu^{1, 2
,},
Han Linfeng¹,
Wen Huiming¹,
Lyu Junfu^{2, 3},
Wang Shuo¹

1.
School of Energy and Power Engineering, University of Shanghai for Science and Technology, Shanghai, 200093, China
2.
Shanxi Research Institute of Huairou Laboratory, Taiyuan, 030032, China
3.
Department of Energy and Power Engineering, Tsinghua University, Beijing, 100084, China

Received Date: 2023-08-14
Rev Recd Date: 2023-10-11
Publish Date: 2024-06-13

Abstract

Abstract

The smooth countercurrent of gas and liquid phases in the hot leg of pressurized water reactor (PWR) is very important to prevent the core melting accident, and the hot leg is composed of horizontal pipe and inclined pipe. In order to determine the constraint mechanism of gas-liquid countercurrent in the hot leg, experiments were carried out on the characteristics of countercurrent flow limitation (CCFL) in inclined and horizontal pipes with ambient air/water as two-phase working medium, and the effects of pipe layout inclination angle (0°~30°) and pipe diameter (40~100 mm) on CCFL in the pipes were studied. The main conclusions are as follows: under the CCFL conditions, the flow pattern in the horizontal pipe shows a typical stratified flow; in the inclined pipe, as the inclination angle and diameter of the pipe increase, stratified flow gradually transits to mist flow. At the same pipe diameter, the CCFL curve characterized by superficial velocities increases with the increase of pipe inclination, which indicates that the gas-liquid countercurrent flow in the hot leg is mainly controlled by the horizontal section. At the same pipe inclination angle, the CCFL curves for both inclined and horizontal pipes increase with the increase of pipe diameter. The conventional Wallis parameters do not reflect the effect of pipe inclination on the CCFL, and also fail to accurately characterize the effect of pipe diameter on the CCFL of horizontal pipes; however, they can correlate the effect of pipe diameter on the CCFL of inclined pipes satisfactorily. Finally, an experimental correlation, which can simultaneously correlate the effects of pipe inclination and diameter, was proposed for the CCFL of inclined pipes. The research results provide basic data and experimental correlation for the safety analysis of PWR nuclear power plant.
- Pressurized water reactor,
- Loss of coolant accident,
- CCFL,
- Inclined pipe,
- Diameter effect

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References(20)

References

[1]	蔡志明,蔡章生. 核动力装置小破口失水事故的瞬态特性模拟与处置研究[J]. 核动力工程,2001, 22(4): 337-341.
[2]	彭云康. 回流流动极限实验研究综述[J]. 核动力工程,1993, 14(6): 556-560.
[3]	GHIAASIAAN S M, WU X, SADOWSKI D L, et al. Hydrodynamic characteristics of counter-current two-phase flow in vertical and inclined channels: effects of liquid properties[J]. International Journal of Multiphase Flow, 1997, 23(6): 1063-1083. doi: 10.1016/S0301-9322(97)00027-X
[4]	ASTYANTO A H, INDARTO K, KIRKLAND K V, et al. An experimental study on the effect of liquid properties on the counter-current flow limitation (CCFL) during gas/liquid counter-current two-phase flow in a 1/30 scaled-down of Pressurized Water Reactor (PWR) hot leg geometry[J]. Nuclear Engineering and Design, 2022, 399: 112052. doi: 10.1016/j.nucengdes.2022.112052
[5]	ZAPKE A, KRÖGER D G. The influence of fluid properties and inlet geometry on flooding in vertical and inclined tubes[J]. International Journal of Multiphase Flow, 1996, 22(3): 461-472. doi: 10.1016/0301-9322(95)00076-3
[6]	ZAPKE A, KRÖGER D G. Countercurrent gas–liquid flow in inclined and vertical ducts-I: Flow patterns, pressure drop characteristics and flooding[J]. International Journal of Multiphase Flow, 2000, 26(9): 1439-1455. doi: 10.1016/S0301-9322(99)00097-X
[7]	ZAPKE A, KRÖGER D G. Countercurrent gas–liquid flow in inclined and vertical ducts-II: The validity of the Froude–Ohnesorge number correlation for flooding[J]. International Journal of Multiphase Flow, 2000, 26(9): 1457-1468. doi: 10.1016/S0301-9322(99)00098-1
[8]	GHIAASIAAN S M, TURK R E, ABDEL-KHALIK S I. Countercurrent flow limitation in inclined channels with bends[J]. Nuclear Engineering and Design, 1994, 152(1-3): 379-388. doi: 10.1016/0029-5493(94)90098-1
[9]	余柳. LN₂-VN₂液泛过程的数值模拟及实验研究[D]. 杭州: 浙江大学,2019.
[10]	陈建业. 倾斜圆管内液氮—氮蒸汽液泛流动特性及临界速度预测方法[D]. 杭州: 浙江大学,2016.
[11]	DEENDARLIANTO N, OUSAKA A, KARIYASAKI A, et al. Investigation of liquid film behavior at the onset of flooding during adiabatic counter-current air-water two-phase flow in an inclined pipe[J]. Nuclear Engineering and Design, 2005, 235(21): 2281-2294. doi: 10.1016/j.nucengdes.2005.03.006
[12]	OUSAKA A, DEENDARLIANTO N, KARIYASAKI A, et al. Prediction of flooding gas velocity in gas–liquid counter-current two-phase flow in inclined pipes[J]. Nuclear Engineering and Design, 2006, 236(12): 1282-1292. doi: 10.1016/j.nucengdes.2005.12.001
[13]	MOUZA A A, PARAS S V, KARABELAS A J. Incipient flooding in inclined tubes of small diameter[J]. International Journal of Multiphase Flow, 2003, 29(9): 1395-1412. doi: 10.1016/S0301-9322(03)00124-1
[14]	MA Y F, SHAO J, LYU J, et al. Experimental study on the effect of diameter on gas–liquid CCFL characteristics of horizontal circular pipes[J]. Nuclear Engineering and Design, 2020, 364: 110645. doi: 10.1016/j.nucengdes.2020.110645
[15]	马有福,邵杰,陆鹏,等. 垂直管内气液两相逆流极限管径效应实验[J]. 核动力工程,2021, 42(1): 28-34.
[16]	ASTYANTO A H, NUGROHO A N A, INDARTO N, et al. Statistical characterization of the interfacial behavior captured by a novel image processing algorithm during the gas/liquid counter-current two-phase flow in a 1/3 scaled down of PWR hot leg[J]. Nuclear Engineering and Design, 2023, 404: 112179. doi: 10.1016/j.nucengdes.2023.112179
[17]	WALLIS G B. One-dimensional two-phase flow[M]. New York: McGraw-Hill, 1969: 336-345.
[18]	PUSHKINA O L, SOROKIN Y L. Breakdown of liquid film motion in vertical tubes[J]. Heat Transfer Soviet Research, 1969, 1(5): 56-64.
[19]	CHEN J Y, XU L, XIONG W, et al. Experimental results of flooding experiments in an inclined tube with liquid nitrogen and its vapor[J]. Cryogenics, 2014, 62: 1-6. doi: 10.1016/j.cryogenics.2014.03.008
[20]	LEE S C, BANKOFF S G. Stability of steam-water countercurrent flow in an inclined channel: Flooding[J]. Journal of Heat Transfer, 1983, 105(4): 713-718. doi: 10.1115/1.3245653