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Volume 43 Issue 3
Jun.  2022
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Li Xing, Wang Qianglong, Tan Sichao, Qiu Jinrong, You Ximing. Research on Distribution Characteristics of Time-averaged Flow Field Downstream of Spacer Grid under Pulsating Flow[J]. Nuclear Power Engineering, 2022, 43(3): 46-52. doi: 10.13832/j.jnpe.2022.03.0046
Citation: Li Xing, Wang Qianglong, Tan Sichao, Qiu Jinrong, You Ximing. Research on Distribution Characteristics of Time-averaged Flow Field Downstream of Spacer Grid under Pulsating Flow[J]. Nuclear Power Engineering, 2022, 43(3): 46-52. doi: 10.13832/j.jnpe.2022.03.0046

Research on Distribution Characteristics of Time-averaged Flow Field Downstream of Spacer Grid under Pulsating Flow

doi: 10.13832/j.jnpe.2022.03.0046
  • Received Date: 2021-05-06
  • Accepted Date: 2021-12-15
  • Rev Recd Date: 2021-06-08
  • Publish Date: 2022-06-07
  • Studying the evolution characteristics of the instantaneous flow field downstream of the spacer grid in the rod bundle channel under flow fluctuation is of great significance to reveal the flow and heat transfer mechanism in the fuel assembly under ocean conditions. In this paper, the structure of the spatio-temporal evolution flow field downstream of the spacer grid in the rod bundle channel under pulsating flow is obtained by using the particle image velocimetry (PIV) technique, and the effects of pulsating parameters (pulsating period and pulsating amplitude) on the velocity distribution and turbulence characteristics downstream of the spacer grid are analyzed. The results show that there is little difference between the time-averaged velocity downstream of the spacer grid under pulsating flow and that under steady flow, and it basically does not change with the variation of pulsating amplitude and pulsating period; The root mean square of transverse velocity and axial velocity downstream of the spacer grid under pulsating flow are significantly different from that under steady flow, and show different trends with the change of pulsating parameters. The results of this paper help to reveal the transient characteristics of fuel assemblies under unsteady conditions and lay a foundation for the design and optimization of fuel assemblies.

     

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  • [1]
    CHUN T H, OH D S. A pressure drop model for spacer grids with and without flow mixing vanes[J]. Journal of Nuclear Science and Technology, 1998, 35(7): 508-510. doi: 10.1080/18811248.1998.9733899
    [2]
    LIU D, GU H Y. Study on heat transfer behavior in rod bundles with spacer grid[J]. International Journal of Heat and Mass Transfer, 2018, 120: 1065-1075. doi: 10.1016/j.ijheatmasstransfer.2017.12.121
    [3]
    YADIGAROGLU G, ANDREANI M, DREIER J, et al. Trends and needs in experimentation and numerical simulation for LWR safety[J]. Nuclear Engineering and Design, 2003, 221(1-3): 205-223. doi: 10.1016/S0029-5493(02)00339-4
    [4]
    王莹杰,王明军,鞠浩然,等. 先进压水堆带定位格架5×5燃料棒束通道热工水力特性CFD数值模拟[J]. 核动力工程,2020, 41(S1): 6-11.
    [5]
    王坤,董秀臣,刘海鹏,等. 小型压水堆压力容器内部三维流场计算[J]. 核动力工程,2020, 41(5): 20-23.
    [6]
    MCCLUSKY H L, HOLLOWAY M V, CONOVER T A, et al. Mapping of the lateral flow field in typical subchannels of a support grid with vanes[J]. Journal of Fluids Engineering, 2003, 125(6): 987-996. doi: 10.1115/1.1625688
    [7]
    HOSOKAWA S, YAMAMOTO T, OKAJIMA J, et al. Measurements of turbulent flows in a 2 × 2 rod bundle[J]. Nuclear Engineering and Design, 2012, 249: 2-13. doi: 10.1016/j.nucengdes.2011.11.035
    [8]
    DOMINGUEZ-ONTIVEROS E E, HASSAN Y A. Non-intrusive experimental investigation of flow behavior inside a 5 × 5 rod bundle with spacer grids using PIV and MIR[J]. Nuclear Engineering and Design, 2009, 239(5): 888-898. doi: 10.1016/j.nucengdes.2009.01.009
    [9]
    DOMINGUEZ-ONTIVEROS E, HASSAN Y A, CONNER M E, et al. Experimental benchmark data for PWR rod bundle with spacer-grids[J]. Nuclear Engineering and Design, 2012, 253: 396-405. doi: 10.1016/j.nucengdes.2012.09.003
    [10]
    DOMINGUEZ-ONTIVEROS E, HASSAN Y A. Experimental study of a simplified 3 × 3 rod bundle using DPTV[J]. Nuclear Engineering and Design, 2014, 279: 50-59. doi: 10.1016/j.nucengdes.2014.04.037
    [11]
    QU W H, WANG Z F, XIONG J B, et al. Experimental study of cross flow and lateral pressure drop in a 5 × 5 rod bundle with mixing vane spacer grid[J]. Nuclear Engineering and Design, 2019, 353: 110209. doi: 10.1016/j.nucengdes.2019.110209
    [12]
    QU W H, XIONG J B, CHEN S L, et al. PIV measurement of turbulent flow downstream of mixing vane spacer grid in 5×5 rod bundle[J]. Annals of Nuclear Energy, 2019, 132: 277-287. doi: 10.1016/j.anucene.2019.04.016
    [13]
    QU W H, XIONG J B, CHEN S L, et al. High-fidelity PIV measurement of cross flow in 5 × 5 rod bundle with mixing vane grids[J]. Nuclear Engineering and Design, 2019, 344: 131-143. doi: 10.1016/j.nucengdes.2019.01.021
    [14]
    封亚. 带搅混翼格架的棒束通道内横向流场PIV实验研究[D]. 北京: 北京交通大学, 2016.
    [15]
    周梦君,毛辉辉,封亚,等. 2×2棒束通道格架搅混翼横向流场PIV实验研究[J]. 核动力工程,2016, 37(4): 133-137.
    [16]
    李兴,祁沛垚,谭思超,等. 脉动流下棒束通道内相位差及瞬态流场研究[J]. 原子能科学技术,2019, 53(8): 1402-1409. doi: 10.7538/yzk.2018.youxian.0808
    [17]
    NISHIO S, OKAMOTO K, KOBAYASHI T, et al. Evaluation of system performance and uncertainty analysis of PIV (PIV-STD project)[C]//Proceedings of the 3rd International Workshop on Particle Image Velocimetry. Santa Barbara: Bulletin of Kobe University of Mercantile Marine, 1999: 465-470
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