Numerical investigation of the effect of mixing vanes on subcooled boiling in a 3 x 3 rod bundle channel with spacer grid

被引:16
作者
Yang, Peng [1 ]
Zhang, Ting [1 ]
Hu, Lulu [1 ]
Liu, Liu [1 ]
Liu, Yingwen [1 ]
机构
[1] Xian Jiaotong Univ1, Sch Energy & Power Engn, Key Lab Thermofluid Sci & Engn MOE, Xian 710049, Shaanxi, Peoples R China
基金
中国博士后科学基金; 国家重点研发计划;
关键词
Mixing vane grid (MVG); Subcooled boiling; Thermal-hydraulic; Lateral disturbance; CFD; CRITICAL HEAT-FLUX; CFD ANALYSIS; TURBULENT-FLOW; CROSS-FLOW; MODEL; VALIDATION; SIMULATION; PREDICTION; DESIGN;
D O I
10.1016/j.energy.2021.121454
中图分类号
O414.1 [热力学];
学科分类号
摘要
Mixing vane grids (MVGs) are an integral part of nuclear reactor fuel assembly, and significantly impact the flow and heat transfer characteristics of the coolant in a rod bundle channel. To investigate the effect of mixing vanes on subcooled flow boiling in the rod bundle channel, a multiphase flow model based on Eulerian was proposed, and was verified by comparing with the experimental data. In addition, the effects of different components in the MVG, deflection angles, and arrangements (of mixing vanes) on the axial distribution of thermal-hydraulic parameters of subcooled boiling in a 3 x 3 rod bundle channel were studied. Compared to other components, mixing vanes exhibited a stronger and more lasting influence on the generation of lateral disturbance, which resulted in a substantial decrease in the values of wall superheat and near-wall void fraction. It was found that with an increase in deflection angle of mixing vanes, the corresponding convective heat transfer increased; however, on exceeding 30 degrees, this tendency decreased significantly. Furthermore, compared to circle-type and series-type arrangement, cross-type arrangement indicated more persistent ability to produce lateral disturbance. (C) 2021 Elsevier Ltd. All rights reserved.
引用
收藏
页数:14
相关论文
共 49 条
  • [1] An investigation of the effect of split-type mixing vane on extent of crossflow between subchannels through the fuel rod gaps
    Agbodemegbe, V. Y.
    Cheng, Xu
    Akaho, E. H. K.
    Allotey, F. K. A.
    [J]. ANNALS OF NUCLEAR ENERGY, 2016, 88 : 174 - 185
  • [2] Antal SP, 1998, INT J MULTIPHAS FLOW, V120, P786
  • [3] Bartolemei G.G., 1967, THERM ENG, V14, P123
  • [4] Bertodano M.L. de., 1991, Turbulent Bubbly Flow in a Triangular Duct
  • [5] Comparison of interfacial heat transfer correlations for high-pressure subcooled boiling flows via CFD two-fluid model
    Braz Filho, Francisco A.
    Fortes, Marco Aurelio
    Ribeiro, Guilherme B.
    [J]. JOURNAL OF THE BRAZILIAN SOCIETY OF MECHANICAL SCIENCES AND ENGINEERING, 2019, 41 (08)
  • [6] Prediction of subcooled flow boiling characteristics using two-fluid Eulerian CFD model
    Braz Filho, Francisco A.
    Ribeiro, Guilherme B.
    Caldeira, Alexandre D.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2016, 308 : 30 - 37
  • [7] Experimental study on the heat transfer enhancement in sub-channels of 6 x 6 rod bundle with large scale vortex flow mixing vanes
    Byun, Sun-Joon
    Shin, Chang-Hwan
    Yoon, Jung
    Kim, Hyungmo
    Lee, Jewhan
    Eoh, Jaehyuk
    Jeong, Ji-Young
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2018, 339 : 105 - 115
  • [8] Thermal-hydraulic performance of a 5 x 5 rod bundle with spacer grid in a nuclear reactor
    Chen, Deqi
    Xiao, Yi
    Xie, Shijie
    Yuan, Dewen
    Lang, Xuemei
    Yang, Zile
    Zhong, Yunke
    Lu, Qi
    [J]. APPLIED THERMAL ENGINEERING, 2016, 103 : 1416 - 1426
  • [9] Experimental study on onset of nucleate boiling and flow boiling heat transfer in a 5 x 5 rod bundle at low flow rate
    Chen, Shuo
    Liu, Da
    Xiao, Yao
    Gu, Hanyang
    [J]. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2019, 137 : 727 - 739
  • [10] Validation of CFD analysis for rod bundle flow test with vaned spacer grids
    Chen, Xi
    Du, Sijia
    Zhang, Yu
    Yu, Hongxing
    Li, Songwei
    Peng, Huanhuan
    Wang, Wei
    Zeng, Wei
    [J]. ANNALS OF NUCLEAR ENERGY, 2017, 109 : 370 - 379