Investigation of pressure loss and velocity distribution in fuel assemblies with wire-wrapped rods by using RANS and LES with wall functions

被引:14
作者
Bieder, U. [1 ]
Uitslag-Doolaard, H. [2 ]
Mikuz, B. [2 ,3 ]
机构
[1] Univ Paris Saclay, CEA, DES STMF, F-91191 Gif Sur Yvette, France
[2] Nucl Res & Consultancy Grp, Westerduinweg 3, NL-1755 LE Petten, Netherlands
[3] Jozef Stefan Inst, Reactor Engn Div, Jamova Cesta 39, Ljubljana 1000, Slovenia
关键词
CFD; Wire-wrapped fuel rods; RANS; LES; Wall function; INTERIOR SUBCHANNELS; TURBULENT FLOWS; HEAT-TRANSFER; BUNDLE;
D O I
10.1016/j.anucene.2020.108025
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
Hexagonal assemblies of wire wrapped fuel rods were analyzed experimentally at Texas A&M University. CFD analysis with LES and RANS (SST k-omega) of a 61-pins experiment have already been published by using wall resolved meshing. These results are compared in this study to CFD calculations with wall functions, more precisely RANS (k-epsilon) and LES. The presented comparison will be used as reference result in the design of RANS based models for the reactor core of sodium cooled fast breeder reactors, since the next generation core models developed at CEA will use CFD models with wall functions. It is shown that the velocity profiles of the analyzed turbulence models are in reasonable accordance to the experiment and among each other. However, RANS with wall functions overestimates the pressure loss in wire wrapped rod bundles. (C) 2020 Elsevier Ltd. All rights reserved.
引用
收藏
页数:15
相关论文
共 27 条
  • [1] Angeli P.-E., 2018, FINITE VOLUMES COMPL, P181
  • [2] Angeli P.-E., 2015, 16 INT TOP M NUCL RE
  • [3] Bieder U, 2010, WORKSH P COMP FLUID, P90
  • [4] CFD analysis of intra and inter fuel assembly mixing
    Bieder, Ulrich
    Genrault, Clarisse
    [J]. ANNALS OF NUCLEAR ENERGY, 2020, 135
  • [5] Analysis of the IAEA benchmark on heat transfer in a 4 x 4 rod bundle with mixing grid
    Bieder, Ulrich
    Costa, Delphine
    [J]. ANNALS OF NUCLEAR ENERGY, 2018, 115 : 352 - 366
  • [6] Brockmeyer L.M., 2015, NURETH 16
  • [7] Review and proposal for best fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlations
    Bubelis, E.
    Schikorr, M.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (12) : 3299 - 3320
  • [8] 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.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2013, 263 : 406 - 410
  • [9] Dovizio D., 2019, PRAGMATIC CFD APPROA
  • [10] Validating RANS to predict the flow behavior in wire-wrapped fuel assemblies
    Dovizio, Daniele
    Mikuz, Blaz
    Shams, Afaque
    Roelofs, Ferry
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2020, 356