Advance Search
Volume 45 Issue 3
Jun.  2024
Turn off MathJax
Article Contents
Wang Zhengquan, Yang Ting, Wen Qinglong, Xu Shijia, Chen Kang, Cheng Cheng, Tang Qionghui. Numerical Study on Heat Transfer Characteristics of a Scaled Model for Horizontal Dry Storage System of Spent Fuel[J]. Nuclear Power Engineering, 2024, 45(3): 68-75. doi: 10.13832/j.jnpe.2024.03.0068
Citation: Wang Zhengquan, Yang Ting, Wen Qinglong, Xu Shijia, Chen Kang, Cheng Cheng, Tang Qionghui. Numerical Study on Heat Transfer Characteristics of a Scaled Model for Horizontal Dry Storage System of Spent Fuel[J]. Nuclear Power Engineering, 2024, 45(3): 68-75. doi: 10.13832/j.jnpe.2024.03.0068

Numerical Study on Heat Transfer Characteristics of a Scaled Model for Horizontal Dry Storage System of Spent Fuel

doi: 10.13832/j.jnpe.2024.03.0068
  • Received Date: 2023-07-26
  • Rev Recd Date: 2023-09-20
  • Publish Date: 2024-06-13
  • Spent fuel dry storage system, with the advantages of safety, economy, and flexibility, is one of the research hotspots in the field of nuclear industry. In this study, the horizontal storage module (HSM) of the spent fuel storage system is taken as the research object, and a three-dimensional natural convection heat transfer model of the 1/2 scale model of the concrete module and the storage container is established by using the physical modeling method combining the conjugate heat transfer technology of computational fluid dynamics (CFD) with porous media, and the flow and heat transfer process in the module is numerically simulated in the Fluent solver. The results show that: the shrinkage structure design at the bottom of the concrete module leads to a sharp increase of the airflow velocity at the inlet section, and the maximum flow velocity is 1.98 m/s. The thermal shielding plate in the concrete module can effectively reduce the temperature of the concrete. The high-temperature area is distributed in the upper part of the back wall of the internal chamber, and the maximum temperature is 108.05℃. The temperature of the fuel assembly shows a symmetric distribution in the axial and horizontal radial direction, and the maximum temperature is 321.97℃. The natural convection heat exchange in concrete module accounts for 82.3% of the total heating power, and its structural design has good heat removal ability. This study will provide important references for scaling experiments and prototype design of spent fuel dry storage systems.

     

  • loading
  • [1]
    NISHIMURA M, SHIBAZAKI H, FUJII S, et al. Natural convection heat transfer in the horizontal dry storage system for the LWR spent fuel assemblies[J]. Journal of Nuclear Science and Technology, 1996, 33(11): 821-828. doi: 10.1080/18811248.1996.9732015
    [2]
    XIE H, GAO Z Y, ZHOU Z W. A numerical investigation of natural convection heat transfer in horizontal spent-fuel storage cask[J]. Nuclear Engineering and Design, 2002, 213(1): 59-65. doi: 10.1016/S0029-5493(01)00454-X
    [3]
    LEE J C, CHOI W S, BANG K S, et al. Thermal-fluid flow analysis and demonstration test of a spent fuel storage system[J]. Nuclear Engineering and Design, 2009, 239(3): 551-558. doi: 10.1016/j.nucengdes.2008.12.015
    [4]
    DAS K, BASU D, SOLIS J, et al. Computational fluid dynamics modeling approach to evaluate VSC–17 dry storage cask thermal designs[C]//CFD for Nuclear Reactor Safety Applications, Workshop Proceedings, CFD4NRS-3. Bethesda, Maryland, USA, 2010: 14-16.
    [5]
    KIM H M, NO H C, BANG K S, et al. Development of scaling laws of heat removal and CFD assessment in concrete cask air path[J]. Nuclear Engineering and Design, 2014, 278: 7-16. doi: 10.1016/j.nucengdes.2014.06.015
    [6]
    WU Y, KLEIN J, ZHOU H, et al. Thermal and fluid analysis of dry cask storage containers over multiple years of service[J]. Annals of Nuclear Energy, 2018, 112: 132-142.
    [7]
    蔡创广. 乏燃料卧式干法贮存热工安全数值模拟与分析[D]. 珠海: 中山大学,2019.
    [8]
    FLUENT A. Theory guide[Z]. Ansys Inc, 2015.
    [9]
    XU Y M, YANG J, XU C, et al. Thermal analysis on NAC-STC spent fuel transport cask under different transport conditions[J]. Nuclear Engineering and Design, 2013, 265: 682-690. doi: 10.1016/j.nucengdes.2013.07.034
    [10]
    KIM H, KWON O J, KANG G U, et al. Comparisons of prediction methods for peak cladding temperature and effective thermal conductivity in spent fuel assemblies of transportation/storage casks[J]. Annals of Nuclear Energy, 2014, 71: 427-435. doi: 10.1016/j.anucene.2014.04.004
    [11]
    DAS K, BASU D, WALTER G R. Thermal analysis of horizontal storage casks for extended storage applications[M]. Washington: United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2014: 1-152.
    [12]
    杨世铭,陶文铨. 传热学[M]. 第四版. 北京: 高等教育出版社,2006: 249-257.
    [13]
    LEMMON E, HUBER M L, MCLINDEN M O. NIST standard reference database 23: reference fluid thermodynamic and transport properties-REFPROP, version 8.0[R]. Gaithersburg: National Institute of Standards and Technology, 2007.
  • 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(10)  / Tables(3)

    Article Metrics

    Article views (54) PDF downloads(42) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return