Computational and experimental methods of investigating the vibration of heat-exchanging steam generator tubes at the nuclear power station

Steam-generating unit is one of the most critical components of the nuclear power station; trouble-free operation of the stations depends on its reliability. One of the most essential components of the steam-generating unit is a tube bundle, since the heat-exchanging tube serves as a natural boundary between the contours of the nuclear power plant. The heat-exchanging tubes breakdown is the main reason for coolant leaks. The article considers the basic methods for investigating the vibration of the heat-exchanging steam generator tubes at the nuclear power station. We show the main mechanisms of the heat-exchanging steam generator tubes vibration generation and highlight the impact of various design and operational factors on the vibration parameters. We provide examples of using the computational and experimental methods of researching the vibration of the heat-exchanging steam generator tubes at the nuclear power station.

References

[1] Douglas J. Solutions for steam generators. EPRI Journal, 1995, no. 3, pp. 28–35.

[2] MacDonald P.E., Shah V.N., Ward L.W., Ellison P.G. Steam generator tube failures. Idaho National Engineering Laboratory, 1996, 307 p.

[3] Alley C.T. Oconee nuclear station unit #1 steam generator discussion with NRC. Washington, 2005, 21 p.

[4] Schneider M. Nuclear France abroad. History, status and prospects of French nuclear activities in foreign countries. Paris, 2009, 49 p.

[5] Chetal S.C., Chellapandi P., Puthiyavinayagam P., Raghupathy S., Balasubramaniyan V., Selvaraj P., Mohanakrishnan P., Raj B. Current status of fast reactors and future plans in India. Energy Procedia, 2011, no. 7, pp. 64–73.

[6] Makhutov N.A., Kaplunov S.M., Pruss L.V. Vibratsiya i dolgovechnost’ sudovogo energeticheskogo oborudovaniya [Vibration and life duration of marine power engineering equipment]. Leningrad, Sudostroenie publ., 1985, 300 p.

[7] Zhukauskas A., Ulinskas R., Katinas V. Gidrodinamika i vibratsii obtekaemykh puchkov trub [Hydrodynamics and vibration of stream-lined pipe bundle]. Vil’nyus, Mokslas publ., 1984, pp. 219–220.

[8] Blevins R.D. Flow induced vibration. Krieger Publ., 2001, 488 p.

[9] Kaplunov S.M., Smirnov L.V., eds. Dinamika konstruktsiy gidroaerouprugikh system [Construction dynamics of aerofluidelastic system]. Moscow, Nauka publ., 2002, 397 p.

[10] Stolotnyuk Ya.D. Razrabotka modeli gidrouprugikh kolebaniy trubnykh puchkov parogeneratorov reaktornykh ustanovok v poperechnom potoke. Diss. kand. tekh. nauk [Model development of pipe bundles fluid-elastic vibrations of reactor facility steam generator in cross-flow. Kand. tech. sci. diss.]. Moscow, Bauman Press, 2004, 199 p.

[11] Hayden O. Design and construction of past and present steam generators for the UK fast reactors. J. Br. Nucl. Energy Soc., 1976, vol. 15, no. 2, pp. 129.

[12] Shin Y.S., Wambsganss M.W. Flow-induced vibration in LMFBR steam generators: a state-of-the-art revie. Nuclear Engineering and Design, 1977, vol. 40, no. 2, pp. 235–284.

[13] Prakash V., Thirumalai M., Prabhakar R., Vaidyanathan G. Assessment of flow induced vibration in a sodium-sodium heat exchanger. Nuclear Engineering and Design, 2009, vol. 239, no. 1, pp. 169–179.

[14] Thirumalai M. Experimental investigation of flow-induced vibration in PFBR steam generator sector model. Int. J. Nuclear Energy Science and Technology, 2007, vol. 3, no. 1, pp. 88–108,

[15] Schlichting H. Grenzschicht-Theorie. Karlsruhe, G. Braun publ., 1951, 483 p. (Russ ed.: Teoriya pogranichnogo sloya. Moscow, Nauka publ., 1974, 712 p.)

[16] Pettigrew M.J., Gorman D.J. Vibration of heat exchanger tube bundles in liquid and two-phase cross-flow. Proc. ASME Pressure Vessel and Piping Conference, 1981, vol. 52, pp. 89–110.

[17] Hartlen R.T., Currie I.G. Lift-oscillator model of vortex-induced vibration. Journal of the Engineering Mechanics Division, 1970, no. 5, pp. 577–591.

[18] Lever J.H., Weaver D.S. A theoretical model for the fluidelastic instability in heat exchanger tube bundles. Journal of Pressure Vessel Technology, 1982, vol. 104, no. 3, pp. 147–158.

[19] Simoneau J.P., Sageaux T., Moussallam T., Bernard O. Fluid structure interaction between rods and a cross flow – numerical approach. Nuclear Engineering and Design, 2011, vol. 241, no. 11, pp. 4515–4522.

[20] Mark A. Christona, Roger Lu, Jozsef Bakosic. Large-eddy simulation, fuel rod vibration and grid-to-rod fretting in pressurized water reactors. Journal of Computational Physics, 2016, vol. 322, pp. 142–161.

[21] Grabaruk A.V., Strelets M.Kh., Shur M.L. Modelirovanie turbulentnosti v raschetakh slozhnykh techeniy [Turbulence simulation in calculations of complex flows]. Sankt-Petersburg, Izd-vo Politekhnicheskogo Universiteta publ., 2012, 88 p.