Advance Search
Volume 44 Issue 4
Aug.  2023
Turn off MathJax
Article Contents
Chen Ling, Wang Xinming, Zhang Yongfa, Zhang Liming, Jiang Lizhi, Jiao Meng, Liu Xiaoya. Analysis of Thermal Stress and Fatigue Induced by Dryout Oscillation in Once Through Steam Generator[J]. Nuclear Power Engineering, 2023, 44(4): 121-127. doi: 10.13832/j.jnpe.2023.04.0121
Citation: Chen Ling, Wang Xinming, Zhang Yongfa, Zhang Liming, Jiang Lizhi, Jiao Meng, Liu Xiaoya. Analysis of Thermal Stress and Fatigue Induced by Dryout Oscillation in Once Through Steam Generator[J]. Nuclear Power Engineering, 2023, 44(4): 121-127. doi: 10.13832/j.jnpe.2023.04.0121

Analysis of Thermal Stress and Fatigue Induced by Dryout Oscillation in Once Through Steam Generator

doi: 10.13832/j.jnpe.2023.04.0121
  • Received Date: 2022-08-16
  • Rev Recd Date: 2023-02-21
  • Publish Date: 2023-08-15
  • In order to study the damage of the heat transfer tube caused by dryout oscillation, the once through steam generator designed by Babcock&Wilcox company is taken as a prototype. Firstly, the relevant thermal and hydraulic parameters are obtained by using the method of primary and secondary side coupled heat transfer. By comparing the radial temperature distribution of dryout point at different fluctuation frequencies, the influence of fluctuation frequency was determined, and the stress distribution of heat transfer tubes was obtained by finite element analysis. Finally, the fatigue of heat transfer tubes was evaluated according to S-N curve, and the influence of related factors was discussed. The results show that when the fluctuation frequency of the drying point is low, the radial temperature distribution is similar to the steady state. The outer wall in contact with the secondary side is more prone to fatigue damage, although the alternating stress is less than the limit value, there is a certain operating risk in the reactor environment. The increase of temperature fluctuation frequency will lead to the obvious decrease of the life of heat transfer tubes, and the use of elastic constraint is helpful to alleviate the fatigue caused by the oscillation of steam drying point. This study provides a reference for the life prediction and safe operation of the heat transfer tubes of once-through steam generator under the condition of fluctuating evaporating point.

     

  • loading
  • [1]
    LIU H T, KAKAC S, MAYINGER F. Characteristics of transition boiling and thermal oscillation in an upflow convective boiling system[J]. Experimental Thermal and Fluid Science, 1994, 8(3): 195-205. doi: 10.1016/0894-1777(94)90048-5
    [2]
    DONG X M, ZHANG Z J, LIU D, et al. Numerical investigation of the effect of grids and turbulence models on critical heat flux in a vertical pipe[J]. Frontiers in Energy Research, 2018, 6: 58. doi: 10.3389/fenrg.2018.00058
    [3]
    DONG X M, DUARTE J P, LIU D, et al. Numerical investigation of azimuthal heat conduction effects on CHF phenomenon in rod bundle channel[J]. Annals of Nuclear Energy, 2018, 121: 203-209. doi: 10.1016/j.anucene.2018.07.033
    [4]
    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
    [5]
    ZENG C J, WANG M J, WU G, et al. Numerical study on the enhanced heat transfer characteristics of steam generator with axial economizer[J]. International Journal of Thermal Sciences, 2022, 182: 107794. doi: 10.1016/j.ijthermalsci.2022.107794
    [6]
    HE S P, WANG M J, TIAN W X, et al. Development of an OpenFOAM solver for numerical simulations of shell-and-tube heat exchangers based on porous media model[J]. Applied Thermal Engineering, 2022, 210: 118389. doi: 10.1016/j.applthermaleng.2022.118389
    [7]
    史建新. 直管式直流蒸汽发生器蒸干及蒸干后传热数值模拟[D]. 哈尔滨: 哈尔滨工程大学, 2019.
    [8]
    肖军,武学素,庄贺庆,等. 快堆蒸汽发生器沸腾传热恶化引起的热应力计算和分析[J]. 核动力工程,1992, 13(3): 63-68.
    [9]
    刘萌萌,张震,杨星团,等. 蒸汽发生器传热管密度波振荡现象研究[J]. 核动力工程,2021, 42(1): 8-14.
    [10]
    KWON J S, KIM D H, SHIN S G, et al. Assessment of thermal fatigue induced by dryout front oscillation in printed circuit steam generator[J]. Nuclear Engineering and Technology, 2022, 54(3): 1085-1097. doi: 10.1016/j.net.2021.09.004
    [11]
    张蕊,田文喜,秋穗正,等. 基于CFD方法的棒束通道内临界热流密度预测[J]. 原子能科学技术,2018, 52(5): 782-787. doi: 10.7538/yzk.2018.52.05.0782
    [12]
    董晓朦. 棒束通道沸腾传热与两相流动CFD分析及应用[D]. 哈尔滨: 哈尔滨工程大学, 2019.
    [13]
    BECKER K M, LING C H, HEDBERG S, et al. Experimental investigation of post dryout heat transfer: KTH-NEL-33.[R]. Stockholm: Royal Institute of Technology, 1983.
    [14]
    SINGH S, DHIR V K. Scaling of the thermal oscillations in the tubes of once through steam generators[C]//ASME. HTD (American Society of Mechanical Engineers. Heat Transfer Div. ). New York: American Society of Mechanical Engineers, 1983, 27: 63-73.
    [15]
    CHIANG T, FRANCE D M, BUMP T R. Calculation of tube degradation induced by dryout instability in sodium-heated steam generators[J]. Nuclear Engineering and Design, 1977, 41(2): 181-191. doi: 10.1016/0029-5493(77)90108-X
    [16]
    ZHANG Y, LU T. Study of the quantitative assessment method for high-cycle thermal fatigue of a T-pipe under turbulent fluid mixing based on the coupled CFD-FEM method and the rainflow counting method[J]. Nuclear Engineering and Design, 2016, 309: 175-196. doi: 10.1016/j.nucengdes.2016.09.021
    [17]
    CHOPRA O K, STEVENS G L, TREGONING R, et al. Effect of light water reactor water environments on the fatigue life of reactor materials[J]. Journal of Pressure Vessel Technology, 2017, 139(6): 060801. doi: 10.1115/1.4035885
  • 加载中

Catalog

    通讯作者: 陈斌, bchen63@163.com
    • 1. 

      沈阳化工大学材料科学与工程学院 沈阳 110142

    1. 本站搜索
    2. 百度学术搜索
    3. 万方数据库搜索
    4. CNKI搜索

    Figures(12)  / Tables(3)

    Article Metrics

    Article views (86) PDF downloads(23) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return