Numerical Investigation of LBE Flow and Heat Transfer Characteristics in Helical-coiled Tube Bundles with Different Coil Strategies

被引：0
|
作者：
Shen C. [1 ]
Liu M. [1 ]
Cheng K. [2 ]
Liu L. [1 ]
Xu Z. [1 ]
Gu H. [1 ]
机构：
[1] School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai
[2] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2023年 / 44卷
关键词：
Coiling direction; Helical tube once-through steam generator (H-OTSG); Lead-bismuth eutectic; Numerical simulation;
D O I：
10.13832/j.jnpe.2023.S1.0057
中图分类号：
学科分类号：
摘要：
Helical tube once-through steam generators (H-OTSG) are widely used in the design of liquid metal reactors, in which adjacent radial tube bundles can be coiled in the same direction or opposite direction, and different coil strategies will affect the flow behavior on the shell side of the steam generator. To explore the lead-bismuth eutectic (LBE) flow and heat transfer characteristics in helical tube bundles with different coil strategies, the shear stress transport (SST k-ω) model, turbulence model and Kays turbulent Prandtl number (Prt) model are used for numerical simulation. First, the numerical method is validated by existing experiments of liquid metal flow cross tube banks. Then, helical-coiled tube bundles with the same coiling direction and alternate coiling direction are established, and the differences in heat transfer and flow resistance are compared. Finally, the reason for the differences is analyzed from the perspective of the flow field. The results show that the flow resistance and heat transfer in the helical-coiled tube bundle with alternate coiling direction are 7.1% and 4.4% higher than those with the same coiling direction respectively. This is due to the stronger turbulent mixing and more uniform velocity field in the alternate-coiled bundle. © 2023 Yuan Zi Neng Chuban She. All rights reserved.
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页码：57 / 61
页数：4
相关论文
共 14 条
  • [1] 3, 5, pp. 52-60, (1982)
  • [2] LI X W, WU X X, HE S Y., Numerical investigation of the turbulent cross flow and heat transfer in a wall bounded tube bundle, International Journal of Thermal Sciences, 75, pp. 127-139, (2014)
  • [3] 42, 7, pp. 1837-1843, (2021)
  • [4] HOE I R, DROPKIN D, DWYER O., Heat-transfer rates to crossflowing mercury in a staggered Tube Bank-I, Transactions of the ASME, 79, 4, pp. 899-905, (1957)
  • [5] RICKARD C L, DWYER O E, DROPKIN D., Heat-transfer rates to cross-flowing mercury in a staggered tube Bank —II, Transactions of the ASME, 80, 3, pp. 646-652, (1958)
  • [6] CESS R D, GROSH R J., Heat transmission to fluids with low prandtl numbers for flow through tube banks, Transactions of the ASME, 80, 3, pp. 677-681, (1958)
  • [7] HSU C J., Analytical study of heat transfer to liquid metals in cross-flow through rod bundles, International Journal of Heat and Mass Transfer, 7, 4, pp. 431-446, (1964)
  • [8] KALISH S, DWYER O E., Heat transfer to NaK flowing through unbaffled rod bundles, International Journal of Heat and Mass Transfer, 10, 11, pp. 1533-1558, (1967)
  • [9] DUAN R Q, JIANG S Y., Numerical investigation of gas flow distribution and thermal mixing in helically coiled tube bundle, Journal of Nuclear Science and Technology, 45, 7, pp. 704-711, (2008)
  • [10] GAO W K, XIE X Y, LI X W, Et al., Influence of coiling direction of helical tube bundles on the thermal-hydraulics of the HTGR steam generator, Journal of Physics:Conference Series, 2048, (2021)
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