Numerical Study of Spacer Effects on Convective Heat Transfer at Low Flow Rates

被引：0

作者：

Ding G. ^{[1
]}

Xiao Y. ^{[1
]}

Gao X. ^{[2
]}

Liu B. ^{[1
]}

Li J. ^{[1
]}

Gu H. ^{[1
]}

机构：

[1] School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai

[2] Nuclear and Radiation Safety Center, Ministry of Ecology and Environment, Beijing

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2022年 / 43卷 / 06期

关键词：

Blocking ratio; Buoyancy lift parameter; Damped oscillation; Heat transfer deterioration; Mixed convection; Spacer effects;

D O I：

10.13832/j.jnpe.2022.06.0008

中图分类号：

学科分类号：

摘要：

A numerical study is carried out for the thermal-hydraulic characteristics of a circular tube with spacer at low flow rates and high heat flux. The convective heat transfer of single-phase water in a smooth circular tube at low flow rates and the spacer effects are calibrated by the empirical correlation and experimental data. A CFD method based on the SST k-ω model is established. The simulation results show that the heat transfer characteristics downstream of the spacer depend on the buoyancy lift parameter. For the forced convection zone and mixed convection heat transfer decreasing zone, the heat transfer downstream of the spacer is always enhanced and the Nussel number decays exponentially. For the mixed convection heat transfer recovery zone and natural convection zone, due to the coupling effect of flow field and heat transfer, the heat transfer downstream of the spacer deteriorates and the Nussel number oscillates with damping. The influence range of heat transfer at the downstream of the spacer first increases and then decreases with the increase of buoyancy lift parameters. The larger the spacer blocking ratio is, the more severe the heat transfer oscillation is, and the worse the heat transfer caused by the spacer is. This study can provide a reference for the design of core in a low-flow core. © 2022 Yuan Zi Neng Chuban She. All rights reserved.

引用

页码：8 / 14

页数：6

共 20 条

[1] WIBISONO A F, AHN Y, WILLIAMS W C, Et al., Studies of various single phase natural circulation systems for small and medium sized reactor design, Nuclear Engineering and Design, 262, pp. 390-403, (2013)
[2] JACKSON J D, COTTON M A, AXCELL B P., Studies of mixed convection in vertical tubes, International Journal of Heat and Fluid Flow, 10, 1, pp. 2-15, (1989)
[3] CARR A D, CONNOR M A, BUHR H O., Velocity, temperature, and turbulence measurements in air for pipe flow with combined free and forced convection, Journal of Heat Transfer, 95, 4, pp. 445-452, (1973)
[4] PARLATAN Y, TODREAS N E, DRISCOLL M J., Buoyancy and property variation effects in turbulent mixed convection of water in vertical tubes, Journal of Heat Transfer, 118, 2, pp. 381-387, (1996)
[5] KESHMIRI A, COTTON M A, ADDAD Y, Et al., Turbulence models and large eddy simulations applied to ascending mixed convection flows, Flow, Turbulence and Combustion, 89, 3, pp. 407-434, (2012)
[6] WU T H, XU Z Y, JACKSON J D., Mixed convection heat transfer to water flowing through a vertical passage of annular cross section: part 2, Chemical Engineering Research and Design, 80, 3, pp. 246-251, (2002)
[7] FOROOGHI P, ABDI I A, DAHARI M, Et al., Buoyancy induced heat transfer deterioration in vertical concentric and eccentric annuli, International Journal of Heat and Mass Transfer, 81, pp. 222-233, (2015)
[8] LIU D, GU H Y., Mixed convection heat transfer in a 5 × 5 rod bundles, International Journal of Heat and Mass Transfer, 113, pp. 914-921, (2017)
[9] LI J L, XIAO Y, GU H Y, Et al., Development of a correlation for mixed convection heat transfer in rod bundles, Annals of Nuclear Energy, 155, (2021)
[10] YAO S C, HOCHREITER L E, LEECH W J., Heat-transfer augmentation in rod bundles near grid spacers, Journal of Heat Transfer, 104, 1, pp. 76-81, (1982)

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