Random excitation forces can cause low-amplitude tube motion that will result in long-term fretting-wear or fatigue. To prevent these tube failures in heat exchangers, designers and troubleshooters must have guidelines that incorporate random or turbulent fluid forces. Experiments designed to measure fluid forces were conducted at the Chalk River Laboratories and at other laboratories worldwide. The data from these experiments were studied and collated, to determine suitable guidelines for random excitation forces. In this paper, a guideline for random excitation forces in single-phase cross flow is presented in the form of normalized spectra that are applicable to a wide range of flow conditions and tube frequencies. In particular, the experimental results used in this study were conducted over the full range of flow conditions found in the liquid region of a nuclear steam generator. The proposed guidelines are applicable to steam generators, condensers, reheaters and other shell-and-tube heat exchangers. They may be used for flow-induced vibration analysis of new or existing components, as input to vibration analysis computer codes and as specifications in procurement documents. [S0094-9930(00)00603-X]

1.
Crandall, S. H., 1958, Random Vibration, Technology Press of MIT Wiley, New York, NY.
2.
Meirovitch, L., 1967, Analytical Methods in Vibration, MacMillan, New York, NY.
3.
Thomson, W. T., 1965, Vibration Theory and Applications, Prentice-Hall, Englewood Cliffs, NJ.
1.
Pettigrew, M. J., and Gorman, D. J., 1973, “Experimental Studies on Flow-Induced Vibration to Support Steam Generator Design, Part 3: Vibration of Small Tube Bundles in Liquid and Two-Phase Cross Flow,” Proc. UKAEA/NPL International Symposium in Vibration Problems in Industry, Keswick, UK, Paper 426;
2.
also, Atomic Energy of Canada Limited Report, AECL-5804.
1.
Antunes, J., 1986, Contribution a` I’Etude des Vibrations de Faiseaux de Tubes en Ecoulement Transversal, doctoral thesis, l’Universite´ de Paris VI, Centre des Etudes Nucle´aires de Saclay, France.
1.
Pettigrew, M. A., and Gorman, D. J. 1978, “Vibration of Heat Exchanger Components in Liquid and Two-Phase Cross Flow,” Proc. BENS International Conference on Vibration in Nuclear Power Plants, Keswick, UK, Paper 2.3;
2.
also, AECL-6184.
1.
Chen
,
S. S.
, and
Jendrzejczyk
,
J.
,
1987
, “
Fluid Excitation Forces Acting on a Square Tube Array
,”
ASME J. Fluids Eng.
,
109
, pp.
415
423
.
2.
Axisa
,
F.
,
Antunes
,
J.
, and
Villard
,
B.
,
1990
, “
Random Excitation of Heat Exchanger Tubes by Cross Flows
,”
J. Fluids Struct.
,
4
, pp.
321
341
.
3.
Taylor
,
C. E.
,
Pettigrew
,
M. J.
,
Axisa
,
F.
, and
Villard
,
B.
,
1988
, “
Experimental Determination of Single- and Two-Phase Cross Flow-Induced Forces on Tube Rows
,”
ASME J. Pressure Vessel Technol.
,
110
, pp.
22
28
.
4.
Oengo¨ren, A., and Ziada, S., 1992, “Unsteady Fluid Forces Acting on a Square Tube Bundle in Air Cross Flow,” 1992 International Symposium on Flow-Induced Vibration and Noise, Vol. 1: FSI/FIV in Cylinder Arrays in Cross Flow, M. P. Paidoussis, W. J. Bryan, J. R. Stenner, and D. A. Steininger, eds., Anaheim, CA, pp. 55–74.
5.
Blevins, R. D., 1990, Flow-Induced Vibration, 2nd Edition, Van Nostrand Reinhold, New York, NY.
6.
Taylor
,
C. E.
,
Pettigrew
,
M. J.
, and
Currie
,
I. G.
,
1996
, “
Random Excitation Forces in Tube Bundles Subjected to Two-Phase Cross Flow
,”
ASME J. Pressure Vessel Technol.
,
118
, pp.
265
277
.
7.
Wolgemuth, G. A., 1994, unpublished data.
8.
Oengo¨ren, A., and Ziada, S., 1995, “Vortex-Shedding, Acoustic Resonance and Turbulent Buffeting in Normal Triangular Tube Arrays”, Proc., 6th International Conference on Flow-Induced Vibration P. W. Bearman, ed., London, UK, pp. 295–313.
9.
Pettigrew
,
M. J.
,
Carlucci
,
L. N.
,
Taylor
,
C. E.
, and
Fisher
,
N. J.
,
1991
, “
Flow-Induced Vibration and Related Technologies in Nuclear Components
,”
Nucl. Eng. Des.
,
131
, pp.
81
100
.
You do not currently have access to this content.