Pressure Drop in Seven-Pin Wire-Wrapped Rod Bundle for the Sodium Cartridge Loop in Versatile Test Reactor

被引:3
|
作者
Quan, Zhengting [1 ]
Dix, Adam [1 ]
Kong, Ran [1 ]
Kim, Seungjin [1 ]
Ishii, Mamoru [1 ]
Farmer, Mitchell T. [2 ]
机构
[1] Purdue Univ, W Lafayette, IN 47907 USA
[2] Argonne Natl Lab, 9700 S Cass Ave, Argonne, IL 60439 USA
关键词
Versatile Test Reactor; hydrodynamics; friction factor; wire-wrapped rod bundle; CFD simulations;
D O I
10.1080/00295639.2022.2082232
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
This work studies the hydrodynamics of the seven pin wire-wrapped rod bundle in the sodium cartridge loop for the Versatile Test Reactor (VTR) through scaled water experiments and computational fluid dynamics (CFD) simulations. The scaling analysis is first performed to demonstrate the hydrodynamic similarity between water and sodium flows at the same Reynolds number Re. A separate-effects test facility is designed and constructed based on the scaling analysis. Detailed experimental data on the pressure drop covering a wide range of Re values (1165 to 27 689) are obtained, which are used to evaluate existing correlations for friction factor and to benchmark CFD simulations. The experimentally determined friction factors f(Exp) agree well with the Upgraded Cheng and Todreas Detailed Correlation and Pacio-Chen-Todreas Detailed Model within +/- 7% but are significantly underpredicted by Rehme's correlation by 25%. Various CFD near-wall treatment methods are tested using ANSYS Fluent and evaluated by experimental data. It is found that when the recommended wall y(+) values are met, most of the near-wall treatment methods can give accurate friction factor predictions. The resolved near-wall method (y(+)similar to 1) with the Shear Stress Transport k - omega turbulence model and the scalable wall functions (y(+) > 12) with the realizable k - epsilon turbulence model can predict f(Exp) within +/- 5% The standard wall functions (y(+) > 30) and nonequilibrium wall functions (y(+) > 30) with the realizable k - s model can predict f(Exp) within +/- 10%.
引用
收藏
页码:771 / 787
页数:17
相关论文
共 11 条
  • [1] An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle
    Liang, Yu
    Zhang, Dalin
    Chen, Yutong
    Zhang, Kui
    Tian, Wenxi
    Qiu, Suizheng
    Su, Guanghui
    APPLIED THERMAL ENGINEERING, 2020, 174
  • [2] Experimental Investigation of Frictional Pressure Drop of Wire-wrapped Bundle at Low Velocity
    Zhou Z.
    Li H.
    Xue X.
    Zeng Z.
    Liu R.
    Liu J.
    Luo R.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2023, 57 (05): : 960 - 967
  • [3] The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles
    Chen, S. K.
    Chen, Y. M.
    Todreas, N. E.
    NUCLEAR ENGINEERING AND DESIGN, 2018, 335 : 356 - 373
  • [4] Flow and temperature developments in a wire-wrapped fuel pin bundle of sodium cooled fast reactor during low flow conditions
    Rasu, N. Govindha
    Velusamy, K.
    Sundararajan, T.
    Chellapandi, P.
    PROGRESS IN NUCLEAR ENERGY, 2015, 81 : 141 - 149
  • [5] Experimental Investigation of the Subchannel Axial Pressure Drop and Hydraulic Characteristics of a 61-Pin Wire Wrapped Rod Bundle
    Menezes, Craig
    Vaghetto, Rodolfo
    Hassan, Yassin A.
    JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME, 2022, 144 (05):
  • [6] Prediction of pressure drop in hexagonal wire-wrapped rod bundles using artificial neural network
    Kim, Hansol
    Chen, Yu Min
    Hassan, Yassin
    NUCLEAR ENGINEERING AND DESIGN, 2021, 381
  • [7] Simultaneous development of flow and temperature fields in wire-wrapped fuel pin bundles of sodium cooled fast reactor
    Rasu, N. Govindha
    Velusamy, K.
    Sundararajan, T.
    Chellapandi, P.
    NUCLEAR ENGINEERING AND DESIGN, 2014, 267 : 44 - 60
  • [8] Numerical Analysis of Hydraulic Characteristic of Fast Reactor Wire-wrapped Rod Bundle Assembly under Low Reynolds Number
    Cheng D.
    Qi X.
    Du K.
    Zhai W.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2019, 53 (08): : 1424 - 1432
  • [9] 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
  • [10] Prediction of flow regime boundary and pressure drop for hexagonal wire-wrapped rod bundles using artificial neural networks
    Kim, Hansol
    Seo, Joseph
    Hassan, Yassin A. A.
    PHYSICS OF FLUIDS, 2022, 34 (10)