Advance Search
Volume 44 Issue S2
Dec.  2023
Turn off MathJax
Article Contents
Yuan Pan, Wang Haoyu, Huang Shan, Liu Menglong, Yue Ti, Ren Quanyao, Qin Mian, Zheng Lele, Guo Zixuan. Research on Thermal-fluid-structure Coupling Behavior for U-10Mo/Al Fuel Assemblies under Irradiation[J]. Nuclear Power Engineering, 2023, 44(S2): 11-16. doi: 10.13832/j.jnpe.2023.S2.0011
Citation: Yuan Pan, Wang Haoyu, Huang Shan, Liu Menglong, Yue Ti, Ren Quanyao, Qin Mian, Zheng Lele, Guo Zixuan. Research on Thermal-fluid-structure Coupling Behavior for U-10Mo/Al Fuel Assemblies under Irradiation[J]. Nuclear Power Engineering, 2023, 44(S2): 11-16. doi: 10.13832/j.jnpe.2023.S2.0011

Research on Thermal-fluid-structure Coupling Behavior for U-10Mo/Al Fuel Assemblies under Irradiation

doi: 10.13832/j.jnpe.2023.S2.0011
  • Received Date: 2023-07-11
  • Rev Recd Date: 2023-07-22
  • Publish Date: 2023-12-30
  • In order to investigate the effects of in-pile mechanical deformation under irradiation on the mechanical and thermal-hydraulic characteristics of U-10Mo/Al fuel assemblies, the mechanical behavior and thermal-hydraulic behavior of U-10Mo/AI fuel assemblies under in-pile irradiation are studied by using the thermal-fluid-structure coupling analysis method under irradiation. By introducing non-uniform irradiation conditions into the irradiation-thermal-mechanical coupling behavior of the 3D finite element model for fuel assemblies, the distribution and evolution laws of structural mechanics field and temperature field of U-10Mo/Al fuel assemblies under time-dependent and location-dependent irradiation conditions are studied. The results show that under the coupling effect of flow field, temperature field, and mechanical mechanics, U-10Mo/AI fuel assemblies exhibit typical mechanical deformation behavior, and both support plates and fuel elements have a certain degree of bending; the temperature field of fuel assemblies show a typical feature of non-uniform spatial distribution, and the peak temperature occurs at the position of maximum swelling of the fuel element; the stress at the sides and corners of the pellet for cladding and the pellet is larger than that in the central region and support plates.

     

  • loading
  • [1]
    KIM Y S, HOFMAN G L. Fission product induced swelling of U–Mo alloy fuel[J]. Journal of Nuclear Materials, 2011, 419(1-3): 291-301. doi: 10.1016/j.jnucmat.2011.08.018
    [2]
    KIM Y S, HOFMAN G L, CHEON J S, et al. Fission induced swelling and creep of U–Mo alloy fuel[J]. Journal of Nuclear Materials, 2013, 437(1-3): 37-46. doi: 10.1016/j.jnucmat.2013.01.346
    [3]
    YAN F, JIAN X B, DING S R. Effects of UMo irradiation creep on the thermo-mechanical behavior in monolithic UMo/Al fuel plates[J]. Journal of Nuclear Materials, 2019, 524: 209-217. doi: 10.1016/j.jnucmat.2019.07.006
    [4]
    JO D, PARK J, CHAE H. Development of thermal hydraulic and margin analysis code for steady state forced and natural convective cooling of plate type fuel research reactors[J]. Progress in Nuclear Energy, 2014, 71: 39-51. doi: 10.1016/j.pnucene.2013.11.006
    [5]
    LI L F, FANG D, ZHANG D L, et al. Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements[J]. Annals of Nuclear Energy, 2019, 134: 284-298. doi: 10.1016/j.anucene.2019.06.030
    [6]
    KENNE J C, SOLBREKKEN G L. Coupled fluid structure interaction (FSI) modeling of parallel plate assemblies[C]//Proceedings of the ASME 2011 International Mechanical Engineering Congress and Exposition. Denver: American Society of Mechanical Engineers, 2011: 159-167.
    [7]
    RICE A. Intercode advanced fuels and cladding comparison using BISON, FRAPCON, and FEMAXI fuel performance codes[D]. Columbia: University of South Carolina, 2015.
    [8]
    HE Y N, CHEN P, WU Y W, et al. Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way[J]. Nuclear Engineering and Design, 2018, 328: 27-35.
    [9]
    LIU R, ZHOU W Z. Multiphysics modeling of novel UO2-BeO sandwich fuel performance in a light water reactor[J]. Annals of Nuclear Energy, 2017, 109: 298-309. doi: 10.1016/j.anucene.2017.05.037
    [10]
    SCHULTHESS J L, LLOYD W R, RABIN B, et al. Mechanical properties of irradiated U-Mo alloy fuel[J]. Journal of Nuclear Materials, 2019, 515: 91-106. doi: 10.1016/j.jnucmat.2018.12.025
    [11]
    MARCHBANKS M F. ANS materials databook: ORNL/M-4582[R]. Oak Ridge: Oak Ridge National Lab. , 1995.
    [12]
    OZALTUN H, SHEN M H H, MEDVEDEV P. Assessment of residual stresses on U10Mo alloy based monolithic mini-plates during Hot Isostatic Pressing[J]. Journal of Nuclear Materials, 2011, 419(1-3): 76-84. doi: 10.1016/j.jnucmat.2011.08.029
  • 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(11)  / Tables(1)

    Article Metrics

    Article views (64) PDF downloads(14) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return