A novel friction factor model for wire-wrapped rod bundles

被引:3
作者
Dix, Adam [1 ]
Kim, Seungjin [1 ]
机构
[1] Purdue Univ, Sch Nucl Engn, Thermal hydraul & Reactor Safety Lab, 363 North Grant Dr, W Lafayette, IN 47907 USA
关键词
Friction factor; Rod bundle; Wire spacer; Laminar geometry constant; PRESSURE-DROP; TURBULENT-FLOW;
D O I
10.1016/j.nucengdes.2022.112104
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
Wire-wrapped rod bundles are often considered for fast spectrum nuclear reactors, especially liquid metal cooled fast reactors (LMFRs). Accurate calculation of the pressure drops of these bundles is key for proper thermal-hydraulic design of the reactor. Existing models, while able to accurately predict bundle friction factor, are complex and can be difficult to use without utilizing a numerical implementation. In this paper, a new model for bundle friction factor is proposed based on exact laminar solutions of the Navier-Stokes equations for a simplified rod bundle geometry. These exact solutions can then be adjusted via geometric and empirical parameters to the prototypic geometry. The proposed model is able to calculate the bundle friction factor with an average absolute percent difference of 10.8 % compared to the available experimental data. This compares favourably to existing correlations, offering similar performance while minimizing the number of empirical coefficients and the overall effort required. The model is also valuable for determining a theoretical lower bound for bundle friction factor for a given geometry, with some data found to be lower (>10 %) than this bound. The overall methodology can also in principal be applied to other geometries where similar simplifications could be made.
引用
收藏
页数:13
相关论文
共 18 条
  • [1] Analytical prediction of turbulent friction factor for a rod bundle
    Bae, Jun Ho
    Park, Joo Hwan
    [J]. ANNALS OF NUCLEAR ENERGY, 2011, 38 (2-3) : 348 - 357
  • [2] Baxi C.B., 1981, Heat Transfer and Fluid Flow in Nuclear Systems, P410
  • [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.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2018, 335 : 356 - 373
  • [4] Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles
    Chen, S. K.
    Todreas, N. E.
    Nguyen, N. T.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2014, 267 : 109 - 131
  • [5] HYDRODYNAMIC MODELS AND CORRELATIONS FOR BARE AND WIRE-WRAPPED HEXAGONAL ROD BUNDLES - BUNDLE FRICTION FACTORS, SUBCHANNEL FRICTION FACTORS AND MIXING PARAMETERS
    CHENG, SK
    TODREAS, NE
    [J]. NUCLEAR ENGINEERING AND DESIGN, 1986, 92 (02) : 227 - 251
  • [6] Kirillov PL., 2010, Handbook of Thermohydraulic Calculations in Nuclear Power Engineering, V1
  • [7] NOVENDSTERN EH, 1972, NUCL ENG DES, V22, P19, DOI 10.1016/0029-5493(72)90059-3
  • [8] Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: The Pacio-Chen-Todreas Detailed model (PCTD)
    Pacio, J.
    Chen, S. K.
    Chen, Y. M.
    Todreas, N. E.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2022, 388
  • [9] Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part II: Evaluation of public experimental data
    Pacio, J.
    Chen, S. K.
    Chen, Y. M.
    Todreas, N. E.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2022, 388
  • [10] Pressure Drop in Seven-Pin Wire-Wrapped Rod Bundle for the Sodium Cartridge Loop in Versatile Test Reactor
    Quan, Zhengting
    Dix, Adam
    Kong, Ran
    Kim, Seungjin
    Ishii, Mamoru
    Farmer, Mitchell T.
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 2023, 197 (05) : 771 - 787