Numerical Simulation of Subcooled Boiling Water in Vertical Concentric Annulus under Low Pressure

陈二锋; 厉彦忠; 王斯民

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Numerical Simulation of Subcooled Boiling Water in Vertical Concentric Annulus under Low Pressure

更新时间：2025-12-08

- Numerical Simulation of Subcooled Boiling Water in Vertical Concentric Annulus under Low Pressure
- Vol. 42, Issue 7, Pages: 855-859(2008)
- 作者机构：
  
  西安交通大学能源与动力工程学院,西安,710049
- 作者简介：
- 基金信息：
- DOI：
  CLC： TL333
- Online First：10 July 2008，
  
  Published：2008
- 稿件说明：
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陈二锋, 厉彦忠, 王斯民. Numerical Simulation of Subcooled Boiling Water in Vertical Concentric Annulus under Low Pressure[J]. 2008, 42(7): 855-859.
DOI：

陈二锋, 厉彦忠, 王斯民. Numerical Simulation of Subcooled Boiling Water in Vertical Concentric Annulus under Low Pressure[J]. 2008, 42(7): 855-859. DOI：

摘要

采用Unal机理模型修正高压工况下气泡脱离直径的Tolubinsky关系式

并以基于有限元的有限容积法的CFX5.7为基本框架

通过添加用户程序实现了低压环管内水过冷沸腾的数值模拟.针对Lee的实验工况分析了过冷沸腾网格无关性的依据

研究了非曳力包括升力、湍流耗散力、壁面润滑力对径向空泡份额分布的影响

验证了模型在宽广工况范围内的适用性.计算表明:当进口过冷度及质量流速较小时

会在出口截面近壁面区域形成空泡份额的峰值

而进口过冷度或质量流速较大时则不会在出口截面近壁面区域形成空泡份额的峰值

这一点是与实验结果相一致的; 液相流速的预测值与实验值较为接近

而气相流速预测值在加热面附近与实验值偏差较大.

Abstract

Adopted a modified bubble departure diameter correlation based on the Unal mechanism model

a numerical simulation of subcooled boiling water under low pressure was performed on the computational fluid dynamics code CFX5.7 with user defined FORTRAN program. The water boiling flow experiments under low pressure in a vertical concentric annulus from reference were adopted to validate the modified model of bubble departure diameter. Moreover

the examination of grid independence was discussed

and the influences of the non-drag force on the radial void fraction distribution force were investigated

including lift force

turbulent dispersion force and wall lubrication force. The simulation results indicate that the models are endowed with a preferable applicability for broad test conditions. Especially

the peak void fraction at near-wall region occurs in low liquid subcooling and low mass flux

contrariwise

the peak void fraction in near-wall region never appears. which is in accordance with the experimental data. The predicted profiles of liquid velocity are close to the experimental data

but obviously differ from the prediction of vapor velocity in the near-wall region.

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references

KURUL N, PODOWSKI M Z. On the modeling of multidimensional effects in boiling channels [C]∥27th National Heat Transfer Conference. Minneapolis, Minnesota, USA: ANS, 1991: 28-31.

BASU N, WARRIER G R, DHIR V K. Onset of nucleate boiling and active nucleation site density during subcooled flow boiling [J].ASME Journal of Heat Transfer, 2002, 124(4): 717-728.

TU Jiyuan. On numerical modeling of low pressure subcooled boiling flows [J]. International Journal of Heat and Mass Transfer, 2002, 45(6): 1197-1209.

KONCAR B, KLJENAK I. Modeling of local two-phase flow parameters in upward subcooled flow boiling at low pressure [J]. International Journal of Heat and Mass Transfer, 2004, 47(6/7): 1499-1513.

ZEITOUN O, SHOUKRI M. Bubble behavior and mean diameter in subcooled flow boiling [J]. ASME Journal of Heat Transfer, 1996, 118(1): 110-116.

UNAL H C. Maximum bubble diameter, maximum bubble-growth time and bubble-growth rate during the subcooled nucleate flow boiling of water up to 17.7 MN/m2[J]. International Journal of Heat and Mass Transfer, 1976, 19(5): 643-696.

KREPPER E, KONCAR B, EGOROV Y. CFD modeling of subcooled boiling-concept, validation and application to fuel assembly design[J]. Nuclear Engineering and Design, 2006, 237(7): 716-731.

LEE T H, PARK G C, LEE D J. Local flow characteristics of subcooled boiling flow of water in a vertical concentric annulus [J]. International Journal of Multiphase Flow, 2002, 28(8): 1351-1368.

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