Numerical study of heat transfer in a distorted rod bundle

被引:1
作者
Chinembiri, Kenneth [1 ]
He, Shuisheng [1 ]
Li, Jiankang [2 ]
Trinca, Cosimo [1 ]
机构
[1] Univ Sheffield, Dept Mech Engn, Heat Flow & Turbulence Res Grp, Sheffield S1 3JD, S Yorkshire, England
[2] EDF Energy Generat, Fuel Route Syst Branch, Engn, Barnett Way, Gloucester GL4 3RS, England
关键词
TURBULENT-FLOW; SIMULATION; BLOCKAGE; CHANNEL;
D O I
10.1016/j.nucengdes.2019.04.003
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
The effect of rod distortion on the flow and heat transfer in a rod (fuel) bundle similar to those in an Advanced Gas-cooled Reactor (AGR) is investigated using carefully constructed CFD models. The results are of relevance to various other engineering applications, for example heat exchangers. The distorted element contracts gradually over the first half of the element, reaching a minimum at half high then subsequently increasing back to its normal value over the second half of the element. In this paper, the results for forced convection are presented. Changes in the rod profiles divert flow to regions of less resistance, resulting in strong cross flow recirculation regions. The resultant three dimensional flow is also accompanied by large scale swirling flow around the fuel pins. The hotspot at any height coincides with the leeward side of the cross flow. It is rather surprising that the peak can temperature at the location of worst bundle distortion (i.e middle height) is actually slightly lower than that of intact fuel. The overall peak can temperature in the damaged bundle is however much higher than that in the intact fuel, and this occurs towards the top of the bundle.
引用
收藏
页码:63 / 77
页数:15
相关论文
共 30 条
[1]   Large Eddy Simulation Study on Forced Convection Heat Transfer to Water at Supercritical Pressure in a Trapezoid Annulus [J].
Amin, Muhsin Mohd ;
Duan, Yu ;
He, Shuisheng .
JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2018, 4 (01)
[2]  
Bogoslovskay A., 1999, IAEATECDOC1060
[3]   EXPERIMENTAL AND ANALYTICAL STUDY OF AXIAL TURBULENT FLOWS IN AN INTERIOR SUBCHANNEL OF A BARE ROD BUNDLE [J].
CARAJILESCOV, P ;
TODREAS, NE .
JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME, 1976, 98 (02) :262-268
[4]   Numerical simulation of turbulent flow in a 37-rod bundle [J].
Chang, D. ;
Tavoularis, S. .
NUCLEAR ENGINEERING AND DESIGN, 2007, 237 (06) :575-590
[5]   Unsteady numerical simulations of turbulence and coherent structures in axial flow near a narrow gap [J].
Chang, D ;
Tavoularis, S .
JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME, 2005, 127 (03) :458-466
[6]   Thermal hydraulics of rod bundles: The effect of eccentricity [J].
Chauhan, Amit K. ;
Prasad, B. V. S. S. S. ;
Patnaik, B. S. V. .
NUCLEAR ENGINEERING AND DESIGN, 2013, 263 :218-240
[7]   Three-dimensional analysis of flow blockage accident in Tehran MTR research reactor core using CFD [J].
Davari, Amin ;
Mirvakili, Seyed Mohammad ;
Abedi, Ebrahim .
PROGRESS IN NUCLEAR ENERGY, 2015, 85 :605-612
[8]   Large eddy simulation of a buoyancy-aided flow in a non-uniform channel - Buoyancy effects on large flow structures [J].
Duan, Y. ;
He, S. .
NUCLEAR ENGINEERING AND DESIGN, 2017, 312 :191-204
[9]  
EDF, 2013, TECH REP
[10]   ON EXPLICIT ALGEBRAIC STRESS MODELS FOR COMPLEX TURBULENT FLOWS [J].
GATSKI, TB ;
SPEZIALE, CG .
JOURNAL OF FLUID MECHANICS, 1993, 254 :59-78