Skip to main content
Log in

Modeling of the Wear of Tube–Spacer Comb Interfacing in the Steam Generator of a Lead-Cooled Reactor

  • Published:
Atomic Energy Aims and scope

One of the predicted disruptions in the normal functioning of steam generators in a lead-cooled reactor over a long period of operation is depressurization of the heat-exchange tubes. The most likely tube failure sites are the tube–spacer comb interfacing zones. The oscillatory motion of the tubes in the lead coolant makes it necessary to study the fretting of the tube material. We describe the structural features of the setup modeling the interaction of the heat-exchange tubes and the spacer comb provided that the heatengineering properties of the lead coolant are the same and the material and structure features of the interfacings are the same. The experimental data on the wear of heat-exchange tubes that serve as the basis for theoretical modeling of their fretting are presented.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Similar content being viewed by others

References

  1. E. D. Fedorovich, B. S. Fokin, A. F. Aksel’rod, and E. N. Gol’dberg, Vibrations of the Components of Equipment in Nuclear Power Facilities, Energoatomizdat, Moscow (1989).

    Google Scholar 

  2. I. V. Kragel’skii, M. N. Dobychin, and V. S. Kombalov, Fundamentals of Friction and Wear Calculations, Mashinostroenie, Moscow (1977).

    Google Scholar 

  3. I. A. Soldatenkov, A. M. Mezrin, and B. Ya. Sachek, “Use of the model of the wear of rigid bodies to identify the wear law on the basis of the results of tribotests,” Trenie i Iznos, 36, No. 6, 683–689 (2015).

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to I. A. Soldatenkov.

Additional information

Translated from Atomnaya Énergiya, Vol. 127, No. 4, pp. 187–191, October, 2019.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Lemekhov, V.V., Sizarev, V.D., Stolotnyuk, S.V. et al. Modeling of the Wear of Tube–Spacer Comb Interfacing in the Steam Generator of a Lead-Cooled Reactor. At Energy 127, 202–206 (2020). https://doi.org/10.1007/s10512-020-00611-9

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-020-00611-9

Navigation