Advance Search
Volume 44 Issue 5
Oct.  2023
Turn off MathJax
Article Contents
Zheng Xu, Sun Lanxin, Huang Junfeng, Zhu Renren, Duan Zhongping, Cheng Xiaoyu, Li Jinrong. Numerical Study on Bending Angle Optimization of Rod Bundle Channel Spacer Grid Mixing Vane Based on Subcooled Boiling CFD[J]. Nuclear Power Engineering, 2023, 44(5): 71-79. doi: 10.13832/j.jnpe.2023.05.0071
Citation: Zheng Xu, Sun Lanxin, Huang Junfeng, Zhu Renren, Duan Zhongping, Cheng Xiaoyu, Li Jinrong. Numerical Study on Bending Angle Optimization of Rod Bundle Channel Spacer Grid Mixing Vane Based on Subcooled Boiling CFD[J]. Nuclear Power Engineering, 2023, 44(5): 71-79. doi: 10.13832/j.jnpe.2023.05.0071

Numerical Study on Bending Angle Optimization of Rod Bundle Channel Spacer Grid Mixing Vane Based on Subcooled Boiling CFD

doi: 10.13832/j.jnpe.2023.05.0071
  • Received Date: 2022-11-02
  • Rev Recd Date: 2022-11-24
  • Publish Date: 2023-10-13
  • The spacer grid is a key component of the fuel assembly. It not only fixes and supports the fuel assembly, but also affects the thermal and hydraulic performance of the fuel assembly. In this paper, the Rensselaer Polytechnic Institute(RPI) wall boiling model based on the Euler-Euler six equations of two fluids is used to carry out a numerical simulation study on the working conditions when subcooled boiling occurs in the 5×5 fuel rod bundle channel; the flow field in the rod bundle channel, the distribution of circumferential wall temperature at different axial heights of the central rod bundle and the distribution of void are obtained. The numerical study results show that the pressure loss of the rod bundle channel increases with the increase of the bending angle of the mixing vane; when the bending angle of the mixing vane is 30°, the proportion of void is relatively small, and the peak temperature of the central rod bundle is relatively low in the downstream of the spacer grid.

     

  • loading
  • [1]
    朱继洲. 核反应堆安全分析[M]. 西安: 西安交通大学出版社, 2000: 408.
    [2]
    YANG R, CHENG B, DESHON J, et al. Fuel R & D to improve fuel reliability[J]. Journal of Nuclear Science and Technology, 2006, 43(9): 951-959. doi: 10.1080/18811248.2006.9711181
    [3]
    陈宝山, 刘承新. 轻水堆燃料元件[M]. 北京: 化学工业出版社, 2007: 385.
    [4]
    郝老迷, 胡古, 郭春秋. 沸腾传热和气液两相流动[M]. 哈尔滨: 哈尔滨工程大学出版社, 2016: 295.
    [5]
    ANGLART H, NYLUND O, KURUL N, et al. CFD prediction of flow and phase distribution in fuel assemblies with spacers[J]. Nuclear Engineering and Design, 1997, 177(1-3): 215-228. doi: 10.1016/S0029-5493(97)00195-7
    [6]
    SALNIKOVA D I T. Two-phase CFD analyses in fuel assembly sub-channels of Pressurized Water Reactors under swirl conditions[J]. Nuclear Engineering and Design, 2010, 68(5): 19-28.
    [7]
    KURUL N, PODOWSKI M Z. Multidimensional effects in forced convection subcooled boiling[C]//Proceedings of the Ninth International Heat Transfer Conference. New York: Hemisphere Publishing, 1990.
    [8]
    肖毅. 带格架燃料组件内复杂流动和传热特性的数值模拟研究[D]. 重庆: 重庆大学, 2016.
    [9]
    KURUL N, PODOWSKI M Z. On the modeling of multidimensional effects in boiling channels[C]//Proceedings of the 27th National Heat Transfer Conference. Minneapolis: ANS, 1991.
    [10]
    ÜNAL 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(6): 643-649. doi: 10.1016/0017-9310(76)90047-8
    [11]
    COLE R. A photographic study of pool boiling in the region of the critical heat flux[J]. AICHE Journal, 1960, 6(4): 533-538. doi: 10.1002/aic.690060405
    [12]
    LEMMERT M, CHAWLA L M. Influence of flow velocity on surface boiling heat transfer coefficient in heat transfer in boiling[J]. International Journal of Applied Engineering Research, 2015, 10(9): 22909-22918.
    [13]
    KOCAMUSTAFAOGULLARI G, ISHII M. Foundation of the interfacial area transport equation and its closure relations[J]. International Journal of Heat and Mass Transfer, 1995, 38(3): 481-493. doi: 10.1016/0017-9310(94)00183-V
    [14]
    DEL VALLE V H, KENNING D B R. Subcooled flow boiling at high heat flux[J]. International Journal of Heat and Mass Transfer, 1985, 28(10): 1907-1920. doi: 10.1016/0017-9310(85)90213-3
    [15]
    MORAGA F J, BONETTO F J, LAHEY R T. Lateral forces on spheres in turbulent uniform shear flow[J]. International Journal of Multiphase Flow, 1999, 25(6-7): 1321-1372. doi: 10.1016/S0301-9322(99)00045-2
  • 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(2)

    Article Metrics

    Article views (111) PDF downloads(86) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return