高级检索

留言板

尊敬的读者、作者、审稿人, 关于本刊的投稿、审稿、编辑和出版的任何问题, 您可以本页添加留言。我们将尽快给您答复。谢谢您的支持!

姓名
邮箱
手机号码
标题
留言内容
验证码

基于单相可压缩模型的蒸汽发生器倒U型管内单相管间脉动特性研究

李振中 马在勇 张舵 步珊珊 孙皖 张卢腾 朱隆祥

李振中, 马在勇, 张舵, 步珊珊, 孙皖, 张卢腾, 朱隆祥. 基于单相可压缩模型的蒸汽发生器倒U型管内单相管间脉动特性研究[J]. 核动力工程, 2022, 43(5): 56-62. doi: 10.13832/j.jnpe.2022.05.0056
引用本文: 李振中, 马在勇, 张舵, 步珊珊, 孙皖, 张卢腾, 朱隆祥. 基于单相可压缩模型的蒸汽发生器倒U型管内单相管间脉动特性研究[J]. 核动力工程, 2022, 43(5): 56-62. doi: 10.13832/j.jnpe.2022.05.0056
Li Zhenzhong, Ma Zaiyong, Zhang Duo, Bu Shanshan, Sun Wan, Zhang Luteng, Zhu Longxiang. Research on Single-phase Inter-tube Pulsation Characteristics in Inverted U-tube of Steam Generator Based on Single-phase Compressible Model[J]. Nuclear Power Engineering, 2022, 43(5): 56-62. doi: 10.13832/j.jnpe.2022.05.0056
Citation: Li Zhenzhong, Ma Zaiyong, Zhang Duo, Bu Shanshan, Sun Wan, Zhang Luteng, Zhu Longxiang. Research on Single-phase Inter-tube Pulsation Characteristics in Inverted U-tube of Steam Generator Based on Single-phase Compressible Model[J]. Nuclear Power Engineering, 2022, 43(5): 56-62. doi: 10.13832/j.jnpe.2022.05.0056

基于单相可压缩模型的蒸汽发生器倒U型管内单相管间脉动特性研究

doi: 10.13832/j.jnpe.2022.05.0056
基金项目: 国家自然科学基金项目(11905021, 51806023)
详细信息
    作者简介:

    李振中(1989—),男,副教授,现从事两相流动换热及流动不稳定性研究工作,E-mail: cqulzz@cqu.edu.cn

    通讯作者:

    马在勇,E-mail: mazy@cqu.edu.cn

  • 中图分类号: TL334

Research on Single-phase Inter-tube Pulsation Characteristics in Inverted U-tube of Steam Generator Based on Single-phase Compressible Model

  • 摘要: 单相工况下的管间脉动现象可使蒸汽发生器倒U型管内倒流现象提前发生,从而威胁其安全性。为探索单相管间脉动特性,基于单相可压缩模型,数值研究了管道长度、一次侧入口温度和压力、二次侧温度和换热系数对单相管间脉动临界流速的影响。结果表明,当管道长度较短时,管道长度的增加会使临界流速显著增加,且倒U型管越长,临界流速越大。一次侧入口温度和压力的增加均会使临界流速增加,使单相管间脉动更易发生。二次侧换热系数的升高会使单相管间脉动对应的临界流速降低。然而二次侧温度对临界流速的影响呈现非单值性,随着二次侧温度的升高,临界流速先升高后降低。

     

  • 图  1  倒U型管单相管间脉动计算模型

    T1,out— 一次侧出口温度;p1,out— 一次侧出口压力

    Figure  1.  Calculation Model of Single-Phase Inter-Tube Pulsation of Inverted U-tube

    图  2  不同入口温度下FE临界流速

    Figure  2.  Critical Velocity of FE under Different Inlet Temperature      

    图  3  单相管间脉动的典型过程

    Figure  3.  Typical Process of Single-phase Inter-Tube Pulsation

    图  4  管道长度对单相管间脉动临界流速的影响

    Figure  4.  Effect of Tube Length on Single-phase Inter-tube Pulsation Critical Velocity

    图  5  一次侧入口温度对临界流速的影响

    Figure  5.  Effect of Primary Side Inlet Temperature on Critical Velocity       

    图  6  一次侧入口过冷度对脉动振幅的影响

    Figure  6.  Effect of Primary Side Inlet Subcooling on Pulsation Amplitude

    图  7  一次侧入口压力对临界流速的影响

    Figure  7.  Effect of Primary Side Inlet Pressure on Critical Velocity     

    图  8  一次侧入口压力对单相管间脉动振幅的影响

    Figure  8.  Effect of Primary Side Inlet Pressure on Single-Phase Inter-Tube Pulsation Amplitude     

    图  9  二次侧温度对单相管间脉动临界流速的影响

    Figure  9.  Effect of Secondary Side Temperature on Single-Phase Inter-Tube Pulsation Critical Velocity

    图  10  二次侧换热系数对临界流速的影响

    Figure  10.  Effect of Secondary Side Heat Transfer Coefficient on Critical Velocity

  • [1] 孙中宁. 核动力设备[M]. 第二版. 哈尔滨: 哈尔滨工程大学出版社, 2017: 25-40.
    [2] ZHAO X H, WANG M J, CHEN C, et al. Three-dimensional study on the hydraulic characteristics under the steam generator (SG) tube plugging operations for AP1000[J]. Progress in Nuclear Energy, 2019, 112: 63-74. doi: 10.1016/j.pnucene.2018.10.016
    [3] ZHAO X H, LIAO Y X, WANG M J, et al. Numerical simulation of micro-crack leakage on steam generator heat transfer tube[J]. Nuclear Engineering and Design, 2021, 382: 111385. doi: 10.1016/j.nucengdes.2021.111385
    [4] 于平安, 朱瑞安, 喻真烷, 等. 核反应堆热工分析[M]. 第三版. 上海: 上海交通大学出版社, 2002: 133-134.
    [5] LEDINEGG M. Instability of flow during natural and forced circulation[J]. Die Waerme, 1938, 61(8): 891-898.
    [6] LORENZINI E. A simplified method proposal for practical determination of aperiodic two-phase flow instability[J]. International Journal of Multiphase Flow, 1981, 7(6): 635-645. doi: 10.1016/0301-9322(81)90035-5
    [7] RUSPINI L C, MARCEL C P, CLAUSSE A. Two-phase flow instabilities: a review[J]. International Journal of Heat and Mass Transfer, 2014, 71: 521-548. doi: 10.1016/j.ijheatmasstransfer.2013.12.047
    [8] HU L, CHEN D Q, HUANG Y P, et al. Numerical investigation of the mechanism of two-phase flow instability in parallel narrow channels[J]. Nuclear Engineering and Design, 2015, 287: 78-89. doi: 10.1016/j.nucengdes.2015.03.009
    [9] 黄彦平,马介亮,肖泽军,等. 多管平行通道管间脉动影响因素试验研究[J]. 核动力工程,2004, 25(4): 314-318,336. doi: 10.3969/j.issn.0258-0926.2004.04.007
    [10] 毕勤成,刘伟民,高峰,等. U型管高压汽-液两相流动密度波型不稳定性的实验研究[J]. 核动力工程,2005, 26(6): 559-562. doi: 10.3969/j.issn.0258-0926.2005.06.007
    [11] SANDERS J. Stability of single-phase natural circulation with inverted U-tube steam generators[J]. Journal of Heat Transfer, 1988, 110(3): 735-742. doi: 10.1115/1.3250553
    [12] JEONG J J, HWANG M, LEE Y J, et al. Non-uniform flow distribution in the steam generator U-tubes of a pressurized water reactor plant during single-and two-phase natural circulations[J]. Nuclear Engineering and Design, 2004, 231(3): 303-314. doi: 10.1016/j.nucengdes.2004.02.002
    [13] LI M R, CHEN W Z, HAO J L, et al. Investigation on reverse flow characteristics in UTSGs with coupled heat transfer between primary and secondary sides[J]. Annals of Nuclear Energy, 2020, 137: 107064. doi: 10.1016/j.anucene.2019.107064
    [14] 王少明,郝建立,章德,等. 蒸汽发生器U型管单相流动不稳定性分析[J]. 原子能科学技术,2016, 50(5): 819-822.
    [15] HAO J L, CHEN W Z, HU G J, et al. Experimental research on reverse flow critical point among parallel U-tubes in SG[J]. Progress in Nuclear Energy, 2017, 98: 59-70. doi: 10.1016/j.pnucene.2017.02.009
    [16] 张锐,马在勇,蒋志鹏,等. 倒U型管蒸汽发生器单相管间脉动现象影响参数研究[J]. 原子能科学技术,2021, 55(8): 1403-1410. doi: 10.7538/yzk.2020.youxian.0545
    [17] 张锐,马在勇,蒋志鹏,等. 倒U型管蒸汽发生器单相管间脉动临界流速与倒流临界流速的对比分析[J]. 核动力工程,2021, 42(5): 36-41. doi: 10.13832/j.jnpe.2021.05.0036
    [18] 田文喜,王明军,秋穗正,等. 基于CFD方法的核动力系统热工安全特性研究进展[J]. 原子能科学技术,2019, 53(10): 1968-1982.
    [19] WANG M J, WANG Y J, TIAN W X, et al. Recent progress of CFD applications in PWR thermal hydraulics study and future directions[J]. Annals of Nuclear Energy, 2021, 150: 107836. doi: 10.1016/j.anucene.2020.107836
    [20] 李龙泽,王明军,田文喜,等. CPR1000全厂断电叠加蒸汽发生器安全阀误开启事故引起的严重事故分析[J]. 原子能科学技术,2014, 48(6): 1020-1025. doi: 10.7538/yzk.2014.48.06.1020
    [21] MA Z Y, ZHANG L T, SUN W, et al. Single-phase density wave oscillation -A new mechanism of flow instability in inverted U-type steam generator[J]. Progress in Nuclear Energy, 2021, 138: 103836. doi: 10.1016/j.pnucene.2021.103836
    [22] 景思睿, 张鸣远. 流体力学[M]. 西安: 西安交通大学出版社, 2006: 175-177.
    [23] 吴鸽平,秋穗正,苏光辉,等. 蒸汽发生器强迫循环流动不稳定性分析[J]. 核动力工程,2006, 27(4): 16-20,25. doi: 10.3969/j.issn.0258-0926.2006.04.005
  • 加载中
图(10)
计量
  • 文章访问数:  187
  • HTML全文浏览量:  37
  • PDF下载量:  34
  • 被引次数: 0
出版历程
  • 收稿日期:  2021-10-25
  • 修回日期:  2022-01-07
  • 刊出日期:  2022-10-12

目录

    /

    返回文章
    返回