Understanding migratory flow caused by helicoid wire spacers in rod bundles: An experimental and theoretical study

被引:14
作者
Bertocchi, F. [1 ]
Rohde, M. [1 ]
Kloosterman, J. L. [1 ]
机构
[1] Delft Univ Technol, Fac Appl Sci, Dept Radiat Sci & Technol, Mekelweg 15, NL-2629 JB Delft, Netherlands
关键词
Rod bundle; Wire-wrap; Particle image velocimetry; Euler equation; NUMERICAL SIMULATIONS; CHANNEL;
D O I
10.1016/j.ijheatfluidflow.2019.108491
中图分类号
O414.1 [热力学];
学科分类号
摘要
The core of a Liquid Metal Fast Breeder Reactor (LMFBR) consists of cylindrical fuel rods that are wrapped by a helicoidally-wound wire spacer to enhance mixing and to prevent damage by fretting. It is known that the liquid metal close to the rod is forced to follow the wires, and that liquid metal further away from the rod crosses the wires (called: migratory flow). This work aims at gaining more insight into the physics behind migratory flow and to provide a model for its bending angle. To this purpose, the flow field in a 7-rods, wire-wrapped, hexagonal bundle with water is studied within the Reynolds number range of 4990-16330 by using Particle Image Velocimetry (PIV). Refraction of the light is minimized by using Fluorinated Ethylene Propylene (FEP), which is a refractive index-matching (RIM) material. These measurements confirm that liquid near the rod follows the helicoid path and bends cross-wise with respect to the wire further away from the rod. A theoretical model for the bending angle of the flow is derived from the Euler equations and shows that the bending is primarily caused by the pressure gradient field induced by the wire. The model shows a very good correspondence with the experimentally obtained PIV data. These findings improve our understanding of the physics at play in rod bundle flows with wrapped wires and can be of assistance in developing practical correlations for frictional pressure losses and heat transfer in such bundles.
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页数:9
相关论文
共 29 条
[1]  
[Anonymous], 2007, Handbook of Experimental Fluid Mechanics
[2]   LDA measurements of coherent flow structures and cross-flow across the gap of a compound channel with two half-rods [J].
Bertocchi, F. ;
Rohde, M. ;
Kloosterman, J. L. .
NUCLEAR ENGINEERING AND DESIGN, 2018, 326 :17-30
[3]   Backward-facing step flows for various expansion ratios at low and moderate Reynolds numbers [J].
Biswas, G ;
Breuer, M ;
Durst, F .
JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME, 2004, 126 (03) :362-374
[4]   Numerical simulations for determination of minimum representative bundle size in wire wrapped tube bundles [J].
Brockmeyer, Landon ;
Carasik, Lane B. ;
Merzari, Elia ;
Hassan, Yassin .
NUCLEAR ENGINEERING AND DESIGN, 2017, 322 :577-590
[5]   Instantaneous planar pressure determination from PIV in turbulent flow [J].
de Kat, R. ;
van Oudheusden, B. W. .
EXPERIMENTS IN FLUIDS, 2012, 52 (05) :1089-1106
[6]  
De Kat R, 2010, P 15 INT S APPL LAS
[7]  
Degroote J., 2016, 11 INT C FLOW IND VI, P1
[8]   Non-intrusive experimental investigation of flow behavior inside a 5 x 5 rod bundle with spacer grids using PIV and MIR [J].
Dominguez-Ontiveros, Elvis E. ;
Hassan, Yassin A. .
NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (05) :888-898
[9]  
Fay J.A., 1994, INTRO FLUID MECH
[10]  
Fischer P., 2007, P JOINT INT TOP M MA