铅铋螺旋管壳侧流动传热数值模拟研究

沈聪; 刘茂龙; 刘利民; 徐子伊; 顾汉洋

doi:10.13832/j.jnpe.2022.S2.0013

铅铋螺旋管壳侧流动传热数值模拟研究

doi: 10.13832/j.jnpe.2022.S2.0013

上海交通大学核科学与工程学院，上海，200240

详细信息

作者简介:
沈　聪（1996—），男，博士研究生，现主要从事铅铋螺旋管安全和优化方面的研究，E-mail: cheneysc@sjtu.edu.cn

中图分类号: TL333
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- 被引次数: 0
出版历程
- 收稿日期: 2022-08-18
- 修回日期: 2022-10-07
- 刊出日期: 2022-12-31

Numerical Simulation of Flow and Heat Transfer in Shell Side of Lead-Bismuth Eutectic Helical Tube

School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240 China

摘要

摘要: 为研究铅铋螺旋管式直流蒸汽发生器（H-OTSG）壳侧的流动传热特性，提出了一种用于螺旋管束内铅铋流动传热特性的数值模拟方法。基于现有的相关实验数据，对不同湍流模型进行了验证，在验证数值模型可靠性的基础上，对铅铋H-OTSG壳侧进行数值模拟，以分析流速和螺旋升角对其传热和阻力特性的影响。结果表明，H-OTSG壳侧流动阻力和换热均随流速和螺旋升角的增大而增强。流速增大会显著增强流场均匀性，螺旋升角增大会影响涡旋分布并加强交混。本研究为铅铋螺旋管流动传热特性研究和设计优化提供参考。
- 铅铋螺旋管 /
- 壳侧 /
- 流动传热 /
- 数值模拟
Abstract: In order to study the flow and heat transfer characteristics in the shell side of LBE Helical-coiled Once-Through Steam Generator (H-OTSG), a numerical method for the simulation of the LBE flow and heat transfer characteristics in helical tube bundles is proposed. Based on available relevant experimental studies, different turbulence models are validated. After validating the reliability of the numerical model, the shell side of LBE H-OTSG is simulated and the influence of velocity and helix angle on heat transfer and flow resistance characteristics are analyzed. The results show that the shell side flow resistance and heat transfer increase with the increase of flow rate and helix angle. An increase in velocity would make the flow fields more uniform. The increase of helix angle affects the vortex distribution and enhances the mixing. This study provides a reference for the study of flow and heat transfer characteristics and design optimization of LBE helical tube.
- LBE helical tube /
- Shell side /
- Flow and heat transfer /
- Numerical simulation

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图 1 液态NaK合金传热特性实验段示意图

Figure 1. Schematic Diagram of Experimental Section of Heat Transfer Characteristics of Liquid NaK Alloy

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图 2 流体计算域示意图

Figure 2. Schematic Diagram of Fluid Calculation Domain

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图 3 RKE和SST模型对于Kalish关系式Nu的预测偏差

下标CFD—CFD计算值；Kalish—Kalish实验值

Figure 3. Prediction Deviation of RKE and SST Models for Kalish Relation Nu

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图 4 RKE和SST模型对于Zukauskas阻力系数的预测偏差

下标Zukauskas—Zukauskas实验值

Figure 4. Prediction Deviation of RKE and SST Models for Zukauskas Resistance Coefficient

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图 5 螺旋管束模型（θ=10°）

Figure 5. Helical Tube Bundle Model (θ=10°)

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图 6 传热计算结果与Hsu关系式的对比

Figure 6. Comparison between Heat Transfer Calculation Results and Hsu Relation

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图 7 不同螺旋升角壳侧结构压降对比

Figure 7. Comparison of Pressure Drop of Shell Side Structure with Different Helix Angles

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图 8 阻力系数计算结果与Zukauskas关系式的对比

Figure 8. Comparison between Calculation Results of Resistance Coefficient and Zukauskas Relation

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图 9 不同Pe下两种壳侧结构的二维流场

Figure 9. 2D Flow Field of Two Shell Side Structures at Different Pe Numbers

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图 10 不同Pe下两种壳侧结构的三维流场

Figure 10. 3D Flow Field of Two Shell Side Structures at Different Pe Numbers

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参考文献(14)

[1]	郭连城, 曹学武. 铅冷快堆（LFR）最新研究进展概述[C]//第六届全国新堆与研究堆学术会议. 伊犁: 中国核学会, 清华大学, 2006: 10-12.
[2]	屠传经,陈学俊. 螺旋管式蒸汽发生器的流动与换热特性[J]. 核动力工程,1982, 3(5): 52-60.
[3]	XIAO Y, HU Z X, CHEN S, et al. Experimental investigation and prediction of post-dryout heat transfer for steam-water flow in helical coils[J]. International Journal of Heat and Mass Transfer, 2018, 127: 515-525.
[4]	XIAO Y, HU Z X, CHEN S, et al. Experimental study of two-phase frictional pressure drop of steam-water in helically coiled tubes with small coil diameters at high pressure[J]. Applied Thermal Engineering, 2018, 132: 18-29. doi: 10.1016/j.applthermaleng.2017.12.074
[5]	XU Z Y, LIU M L, XIAO Y, et al. Development of a RELAP5 model for the thermo-hydraulic characteristics simulation of the helically coiled tubes[J]. Annals of Nuclear Energy, 2021, 153: 108032. doi: 10.1016/j.anucene.2020.108032
[6]	SHAMS A, DE SANTIS A, KOLOSZAR L K, et al. Status and perspectives of turbulent heat transfer modelling in low-Prandtl number fluids[J]. Nuclear Engineering and Design, 2019, 353: 110220. doi: 10.1016/j.nucengdes.2019.110220
[7]	HOE R J, DROPKIN D, DWYER O E. Heat-transfer rates to crossflowing mercury in a staggered Tube Bank-I[J]. Transactions of the American Society of Mechanical Engineers, 1957, 79(4): 899-905.
[8]	RICKARD C L, DWYER O E, DROPKIN D. Heat-transfer rates to cross-flowing mercury in a staggered tube bank—II[J]. Transactions of the American Society of Mechanical Engineers, 1958, 80(3): 646-652.
[9]	CESS R, GROSH R. Heat transmission to fluids with low prandtl numbers for flow through tube banks[J]. Transactions of the American Society of Mechanical Engineers, 1958, 80(3): 677-681.
[10]	CHIA-JUNG H. Analytical study of heat transfer to liquid metals in cross-flow through rod bundles[J]. International Journal of Heat and Mass Transfer, 1964, 7(4): 431-446. doi: 10.1016/0017-9310(64)90135-8
[11]	KALISH S, DWYER O E. Heat transfer to NaK flowing through unbaffled rod bundles[J]. International Journal of Heat and Mass Transfer, 1967, 10(11): 1533-1558. doi: 10.1016/0017-9310(67)90006-3
[12]	SHIH T H, LIOU W W, SHABBIR A, et al. A new k-ε eddy viscosity model for high reynolds number turbulent flows-model development and validation[J]. Computers & Fluids, 1995, 24(3): 227-238.
[13]	MENTER F R. Two-equation eddy-viscosity turbulence models for engineering applications[J]. AIAA Journal, 1994, 32(8): 1598-1605. doi: 10.2514/3.12149
[14]	ŽUKAUSKAS A, ULINSKAS R. Efficiency parameters for heat transfer in tube banks[J]. Heat Transfer Engineering, 1985, 6(1): 19-25. doi: 10.1080/01457638508939614