Skip to main content
Log in

Seal assessment of the first-loop equipment in a propulsion nuclear power system during hydraulic tests

  • Published:
Atomic Energy Aims and scope

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.

References

  1. D. F. Romanov, M. A. Lebedev, S. S. Savarenskii, and N. P. Shamanov, Ship Nuclear Steam Generating Systems, Sudostroenie, Leningrad (1967).

    Google Scholar 

  2. F. Ya. Ovchinnikov, L. I. Golubev, V. D. Dobrynin, et al., Operational Regimes of Water-Moderated Water-Cooled Reactors, Atomizdat, Moscow (1977).

    Google Scholar 

  3. V. A. Boltenkov, V. I. Vertepa, O. V. Maslov, and M. V. Maksimov, “Trends, problems, and prospects for the development of systems for monitoring small flows in the top block of the reactor unit of a nuclear power plant,” Avtom., Avtomatizats., Élektrotekh. Kompl. Syst., No. 1, 139–146 (1999).

  4. V. Ya. Bredikhin and A. A. Zmitrodan, “Monitoring the interloop density of a propulsion nuclear power system cooled by pressurized water,” At. Énerg., 98, No. 3, 170–175 (2005).

    Article  Google Scholar 

  5. V. V. Badyaev, Yu. A. Egorov, V. P. Sklyarov, and G. F. Stegachev, “Tritium at nuclear power plants,” in: Radiation Safety and Shielding of Nuclear Power Plants, Atomizdat, Moscow (1981), No. 5, pp. 64–77.

    Google Scholar 

  6. L. A. Lenskii, Tritium Physics and Chemistry, Énergoizdat, Moscow (1981).

    Google Scholar 

  7. L. F. Belovodskii, V. K. Gaevoi, and V. I. Grishmanovskii, Tritium, Énergoatomizdat, Moscow (1985).

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Additional information

__________

Translated from Atomnaya Énergiya, Vol. 101, No. 6, pp. 448–450, December, 2006.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Bredikhin, V.Y., Zmitrodan, A.A. Seal assessment of the first-loop equipment in a propulsion nuclear power system during hydraulic tests. At Energy 101, 905–907 (2006). https://doi.org/10.1007/s10512-006-0190-5

Download citation

  • Received:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-006-0190-5

Keywords

Navigation