The blockage model of Upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles

被引:4
|
作者
Chen, Y. M. [1 ]
Chen, S. K. [2 ]
Hassan, Y. [1 ]
机构
[1] Texas A&M Univ TAMU, Dept Nucl Engn, College Stn, TX 77845 USA
[2] Natl Tsing Hua Univ NTHU, Inst Nucl Engn & Sci, Hsinchu 30013, Taiwan
关键词
HEAT-TRANSFER; 19-ROD BUNDLE; FLOW;
D O I
10.1016/j.nucengdes.2022.111874
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A model to predict the pressure drops in a hexagonal wire-wrapped rod bundle with blockage is developed. The model is based on the Upgraded Cheng and Todreas Detailed (UCTD) correlation. Two series of experiments from Texas A & M University (TAMU) and Karlsruhe Institute of Technology (KIT) are used for calibration and validation. The UCTD correlation for drag and swirl forces are modified to account the presence of the blockage. The characteristic velocity of the Reynolds number is revised. The pressure drop is well predicted in the turbulent flow regime with a mean error less than 3%. The friction factor of transition flow regime is an interpolation between laminar and turbulent. Due to the lack of data in laminar flow regime, the mean error in the transition regime is higher than 5%. Overall, the mean errors of the two validation cases are 2.5% and-0.6%, and the root mean square (RMS) errors are 3.2% and 7.2%. To improve the accuracy and extend the ability to predict complex blockage conditions such as blocked thickness or porosity, a variety and an amount of experimental data are needed.
引用
收藏
页数:7
相关论文
共 50 条
  • [41] Implementation of a CFD methodology for computing subchannel friction factors and split parameters in wire-wrapped rod bundles
    Bovati, Octavio
    Hassan, Yassin
    Nuclear Engineering and Design, 2022, 397
  • [42] Implementation of a CFD methodology for computing subchannel friction factors and split parameters in wire-wrapped rod bundles
    Bovati, Octavio
    Hassan, Yassin
    NUCLEAR ENGINEERING AND DESIGN, 2022, 397
  • [43] Numerical implementation of the Cheng and Todreas correlation for wire wrapped bundle friction factors-desirable improvements in the transition flow region
    Chen, S. K.
    Petroski, R.
    Todreas, N. E.
    NUCLEAR ENGINEERING AND DESIGN, 2013, 263 : 406 - 410
  • [44] Effect of bubble entrainment on thermal-hydraulic performance of LBE-cooled wire-wrapped rod bundles
    Wu, Chunxi
    Liu, Li
    Luo, Haotian
    Bao, Ruiqi
    Yuan, Junjie
    Liu, Maolong
    Gu, Hanyang
    ANNALS OF NUCLEAR ENERGY, 2025, 214
  • [45] POROUS BODY MODEL FOR PREDICTING TEMPERATURE DISTRIBUTION IN WIRE-WRAPPED FUEL ROD ASSEMBLIES
    KHAN, EU
    ROHSENOW, WM
    SONIN, AA
    TODREAS, NE
    NUCLEAR ENGINEERING AND DESIGN, 1975, 35 (01) : 1 - 12
  • [46] CFD analysis of flow blockage phenomena in a LBE-cooled 19-pin wire-wrapped rod bundle
    Chai, Xiang
    Liu, Xiaojing
    Xiong, Jinbiao
    Cheng, Xu
    NUCLEAR ENGINEERING AND DESIGN, 2019, 344 : 107 - 121
  • [47] Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle
    Melsheimer, Trevor
    Menezes, Craig
    Hassan, Yassin A.
    NUCLEAR TECHNOLOGY, 2025, 211 (04) : 725 - 741
  • [48] Static pressure and wall shear stress distributions in air flow in a seven wire-wrapped rod bundle
    Fernandez Y Fernandez, Elói
    Carajilescov, Pedro
    Revista Brasileira de Ciencias Mecanicas/Journal of the Brazilian Society of Mechanical Sciences, 2000, 22 (02): : 291 - 302
  • [49] Heat transfer from a 2 x 2 wire-wrapped rod bundle to supercritical pressure water
    Wang, Han
    Bi, Qincheng
    Leung, Laurence K. H.
    INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2016, 97 : 486 - 501
  • [50] A comparative analysis of detailed and reduced CFD approaches to model wire-wrapped fuel bundles for LMFBRs applications
    Halim, O.
    Galleni, F.
    Forgione, N.
    Di Piazza, I.
    Pucciarelli, A.
    ANNALS OF NUCLEAR ENERGY, 2025, 211