定位格架对单棒通道欠热流动沸腾影响的数值研究

张廷; 吕梦欣; 刘洪江; 支长双; 陈鹏帆; 刘迎文

doi:10.7652/xjtuxb202012014

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定位格架对单棒通道欠热流动沸腾影响的数值研究

更新时间：2025-07-09

- 定位格架对单棒通道欠热流动沸腾影响的数值研究
- Numerical Investigation to Effect of Spacer Grid on the Subcooled Flow Boiling in Single Rod Channel
- 西安交通大学学报 2020年54卷第12期页码：116-124
- 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：
  
  : 2020-05-15。作者简介: 张廷(1992—),男,硕士生;刘迎文(通信作者),男,教授。基金项目: 国家重点研发计划资助项目(2018YFB1900402);国家自然科学基金资助项目(51976164)
- DOI：10.7652/xjtuxb202012014
  中图分类号： TK172;TL333
- 网络首发：2020-12-10，
  
  纸质出版：2020
- 稿件说明：
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张廷, 吕梦欣, 刘洪江, 等. 定位格架对单棒通道欠热流动沸腾影响的数值研究[J]. 西安交通大学学报, 2020,54(12):116-124.

Numerical Investigation to Effect of Spacer Grid on the Subcooled Flow Boiling in Single Rod Channel[J]. 2020, 54(12): 116-124.
张廷, 吕梦欣, 刘洪江, 等. 定位格架对单棒通道欠热流动沸腾影响的数值研究[J]. 西安交通大学学报, 2020,54(12):116-124. DOI： 10.7652/xjtuxb202012014.

Numerical Investigation to Effect of Spacer Grid on the Subcooled Flow Boiling in Single Rod Channel[J]. 2020, 54(12): 116-124. DOI： 10.7652/xjtuxb202012014.

摘要

为了研究定位格架对燃料棒束通道内冷却剂热工水力特性的影响规律

选取5×5棒束通道中心的一根燃料棒及定位格架进行数值研究。建立了基于欧拉两流体六方程的带定位格架的竖直单燃料棒通道内冷却剂欠热沸腾多相流模型

并实验比较验证了模型的准确性

获得了带定位格架与不带定位格架的单燃料棒通道内发生欠热沸腾时相关热力参数的空间分布特征

揭示了定位格架对欠热沸腾流动及换热特性的影响规律。结果发现:相较无定位格架结构

引入定位格架及搅混翼后

流场和温度场发生了不同程度的逆时针旋转

平均二次流最大值能达到进口速度的13.5%

局部二次流强度可达到60%

整体压降仅增加5%; 定位格架显著增大了液相对流热流密度

最大增幅为44.3%

导致液相过冷度、壁面过热度和气体体积分数的进一步降低

从而增强了核反应堆的安全性。

Abstract

To investigate the influence of spacer grid on the thermal-hydraulic characteristics of coolant in fuel rod bundle channel

a single fuel rod and a spacer grid in the center of 5×5 bundle channel are selected for the numerical analysis. Following Eulerian theory

a mathematical model of multiphase flow for the subcooled boiling of coolant in a vertical single rod channel is established. The accuracy of the model is verified by a comparison of numerical simulation results with experiment data. The spatial distribution characteristics of the relevant thermal parameters in the single rod channel with or without spacer grid are obtained

and the influence of spacer grid on the flow and heat transfer characteristics of subcooled boiling is revealed. The results show that compared with the rod channel without spacer grid

the flow field and temperature field rotate anticlockwise in a certain degree after passing through the spacer grid and the mixing wings. The maximum value of the average secondary flow can reach 13.5% of the inlet velocity

and the local secondary flow can reach 60%. The pressure drop of the whole device with spacer grid is only 5% higher than that without spacer grid. The spacer grid can significantly make liquid phase convection heat flux increase

and the maximum increase can reach 44.3%. As a result

the liquid subcooling

wall superheat and vapor volume fraction are further reduced

thus enhancing the safety of nuclear reactor.

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references

郝老迷. 核反应堆热工水力学 [M]. 北京: 原子能出版社, 2010: 107-116

米争鹏, 谭思超, 邹思远, 等. 棒束通道内温度场分布特性研究 [J]. 原子能科学技术, 2020, 54(9): 1644-1652.

MI Zhengpeng, TAN Sichao, ZOU Siyuan, et al. Temperature field distribution characteristics in rod bundle channel [J]. Atomic Energy Science and Technology, 2020, 54(9): 1644-1652.

NAVARRO M A, SANTOS A A C. Evaluation of a numeric procedure for flow simulation of a 5×5 PWR rod bundle with a mixing vane spacer [J]. Progress in Nuclear Energy, 2011 53(8): 1190-1196.

CHENG S B, CHEN H D, ZHANG X Y. CFD analysis of flow field in a 5×5 rod bundle with multi-grid [J]. Annals of Nuclear Energy, 2017 99: 464-470.

陈曦, 张虹. 压水堆棒束定位格架两相搅混特性数值研究 [J]. 原子能科学技术, 2014, 48(9): 1589-1595.

CHEN Xi, ZHANG Hong. Numerical study of two-phase mixing characteristics on PWR rod bundle with spacer grid [J]. Atomic Energy Science and Technology, 2014, 48(9): 1589-1595.

BARTOLOMEI G G, CHANTURIYA V M. Experimental study of true void fraction when boiling subcooled water in vertical tubes [J]. Thermal Engineering, 1967, 14(2): 123-128.

BARTEL M D. Experimental investigation of subcooled boiling [D]. West Lafayette, USA: Purdue University, 1999: 65-97.

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.

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

彭伟頔, 郑乐乐, 卢川, 等. 泡核沸腾两相CFD模拟的参数敏感性分析与模型验证 [J]. 核科学与工程, 2018, 38(2): 194-204.

PENG Weidi, ZHENG Lele, LU Chuan, et al. Parameter sensitivity analysis and model verification of two-phase CFD simulation in nucleate boiling [J]. Nuclear Science and Engineering, 2018, 38(2): 194-204.

KUMAR M, MOHARANA A, NAYAK A K, et al. CFD simulation of boiling flows inside fuel rod bundle of a natural circulation BWR during SBO [J]. Nuclear Engineering and Design, 2018, 338: 300-329.

ISHII M, ZUBER N. Drag coefficient and relative velocity in bubbly, droplet or particulate flows [J]. AIChE Journal, 1979, 25: 843-855.

DREW D A, LAHEY R T. The virtual mass and lift force on a sphere in rotating straining inviscid flow [J]. International Journal of Multiphase Flow, 1987, 13(1): 113-121.

TOMIYAMA A. Struggle with computational bubble dynamics [C]∥Third International Multiphase Flow. Lyon, France: [s.n.], 1998: 1-18.

PODOWSKI M Z, KURUL N. Multidimensional effects in forced convective subcooled boiling [C]∥9th International Heat Transfer Conference. Jerusalem, Israel: [s.n.], 1990: 21-26.

RANZ W E, MARSHALL W R. Evaporation from drops [J]. Chemical Engineering Progress, 1952, 48(1): 141-146.

JUDD R L, HWANG K S. A comprehensive model for nucleate pool boiling heat transfer including microlayer evaporation [J]. ASME J Heat Transfer, 1976, 94(4): 623-629.

MIKIC B, ROHSENOW W M. A new correlation of pool boiling data including the fact of heating surface characteristics [J]. ASME J Heat Transfer, 1969, 91(2): 245-250.

TOLUBINSKY V I, KOSTANCHUK D M. Vapor bubbles growth rate and heat transfer intensity at subcooled water boiling [C]∥Fourth International Heat Transfer Conference. Paris, France: [s.n.], 1970: B-28.

ANGLART H NYLUND O. CFD application to prediction of void distribution in two-phase bubbly flows in rod bundles [J]. Nuclear Engineering and Design 1996, 163(1/2): 81-98.

LO S, RAO P. Modeling of droplet breakup and coalescence in an oil-water pipeline [C]∥6th International Conference on Multiphase Flow. Leipzig, Germany: ICMF, 2007: 9-13.

LEMMERT M, CHWALA J M. Influence of flow velocity on surface boiling heat transfer coefficient [M]. New York, USA: Academic Press and Hemisphere, 1977: 111-116.

COLE R. A photographic study of pool boiling in the region of the critical heat flux [J]. AIChE Journal, 1960, 6(4): 533-538.

GAO Y P, SHAO S Q, XU H B, et al. Numerical investigation on onset of significant void during water subcooled flow boiling [J]. Applied Thermal Engineering, 2016, 105: 8-17.

MIMOUNI S, BAUDRY C, GUINGO M, et al. Computational multi-fluid dynamics predictions of critical heat flux in boiling flow [J]. Nuclear Engineering and Design, 2016, 299: 28-36.

ZHANG R, CONG T L, TIAN W X, et al. Effects of turbulence models on forced convection subcooled boiling in vertical pipe [J]. Annals of Nuclear Energy, 2015, 80: 293-302.

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