EXPERIMENTAL INVESTIGATION OF FLOW RESISTANCE AND WALL SHEAR-STRESS IN THE INTERIOR SUBCHANNEL OF A TRIANGULAR ARRAY OF PARALLEL RODS

被引:11
作者
FAKORY, M
TODREAS, N
机构
[1] Department of Nuclear Engineering, Rensselaer Polytechnic Institute, Troy, NY
[2] Massachussets Institute of Technology, Cambridge, MA
来源
JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME | 1979年 / 101卷 / 04期
关键词
D O I
10.1115/1.3449003
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
A simulated model of a triangular array of rods with pitch to diameter ratio of 1.1 with airflow was used to study the hydraulic parameters of the liquid metal fast breeder reactor (LMFBR) fuel geometry. The wall shear stress distribution, static pressure distribution, turbulence intensity, and friction factor were measured in the central subchannel from Reynolds numbers of 4 x 103 to 36 x 103. Our results show that the maximum wall shear stress occurs at the largest flow area, the static pressure is not uniform around the rod periphery, there is no detectable presence of secondary flow from the wall shear stress measurements, and the friction factor derived from the measured wall shear stress is less than the common friction factor derived from pressure drop measurement. © 1979 by ASME.
引用
收藏
页码:429 / 435
页数:7
相关论文
共 18 条
[1]  
Levchenko Y.S., Subbotin V.I., The Distribution of Coolant Velocities and Wall Stresses in Closely Packed Rods, Sov. Atom. Energy, 23, 3, pp. 218-225, (1967)
[2]  
Subbotin V.I., Et al., Velocity Field of Turbulent Fluid Flow in a Longitudinal Streamline of Rods, (1971)
[3]  
Gerard R., Baines W., Turbulent Flow in Very Noncircular Conduit, Journal of the Hydraulic Division, Proceeding of the ASCE, 103, 8, pp. 829-842, (1977)
[4]  
Trupp A.C., Azad R.S., The Structure of Turbulent Flow in Triangular Array Rod Bundles, Nucl. Eng. and Design, 32, 1, pp. 47-84, (1975)
[5]  
Simonek I., Mrakava J., Experimental Study of the Distribution of the Wall Shear Stress and the Velocity Field in the Channel of an Infinite Array Rods, Czechoslovak Atomic Energy Commission, Prague International Conference on Simulation Techniques in the Investigation of Thermokinetic Effects in the Core of Fast Reactors, (1971)
[6]  
Rehme K., Anisotropic Eddy Viscosities in the Turbulent Flow through a Rod Bundle, (1977)
[7]  
Fakory M.R., Measurement and Analysis of Flow Resistance and Wall Shear Stress in an Interior Subchannel of a Triangular Array Rods, (1977)
[8]  
Bartzis J.G., Hydrodynamic Behavior of a Bare Rod Bundle, (1977)
[9]  
Patel V.C., Calibration of the Preston Tube and Limitation on its Use in Pressure Gmdiants, J. FluidMech, 23, pp. 185-208, (1965)
[10]  
Eifler W., Limitation on the Use of Preston Tubes in Channel Flow, Warme-Und-Stoffubertragung, (1970)