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Wear of the pipe-spacing grating pair of a steam generator in a lead heat carrier

  • Reliability, Durability, and Wear Resistance of Machines and Constructions
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Abstract

The results of the solution of tribological problems emerging when friction units operate in heavy liquid metals as heat carriers in nuclear power plants are presented. An installation has been developed to simulate the vibrational wear of friction units in heat exchanging tubes of interfaced units with spacing gratings in order to simulate resistance to the vibration of the steam generator of a fast neutron reactor with lead heat carriers. A method of study has been developed, samples of tubes and spacing gratings have been tested for vibrational wear, and metallographic and profilometric exploration has been performed. The wear mechanism is described and the tentative life of the steam generator pipes is assessed.

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References

  1. Drozdov, Yu.N., Pavlov, V.G., and Puchkov, V.N., Trenie i iznos v ekstemal’nykh usloviyakh. Spravochnik. Ser. Osnovy proektirovaniya mashin (Friction and Wear under Extreme Conditions. Handbook. Series: Foundations of Machines Design), Moscow: Mashinostroenie, 1986.

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  2. Beznosov, A.V., Dragunov, Yu.G., and Rachkov, V.I., Tyazhelye zhidkometallicheskie teplonositeli v atomnoi energetike (Heavy Liquid-Metal Coolants Used in Nuclear Power Engineering), Moscow: Izd-vo AT, 2007.

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  3. Drozdov, Yu.N., The Way to Determine the Wear Rate of Machine Elements, Vestnik mashinostroeniya, 1980, no. 6, pp. 12–15.

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Original Russian Text © Yu.N. Drozdov, A.V. Beznosov, V.V. Makarov, V.N. Puchkov, M.A. Antonenkov, D.V. Kuznetsov, 2009, published in Problemy Mashinostroeniya i Mashin, 2009, No. 5, pp. 61–66.

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Drozdov, Y.N., Beznosov, A.V., Makarov, V.V. et al. Wear of the pipe-spacing grating pair of a steam generator in a lead heat carrier. J. Mach. Manuf. Reliab. 38, 467–471 (2009). https://doi.org/10.3103/S1052618809050100

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  • DOI: https://doi.org/10.3103/S1052618809050100

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