Skip to main content
Log in

Purification of the first circuit of nuclear power systems with a two-component coolant-gas flow

  • Articles
  • Published:
Soviet 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.

Literature Cited

  1. I. K. Morozova et al., Removal and Deposition of the Corrosion Products of Reactor Materials [in Russian], Atomizdat, Moscow (1975).

    Google Scholar 

  2. P. Cohen, The Technology of the Water in Power Reactors [Russian translation], Atomizdat, Moscow (1973).

    Google Scholar 

  3. V. A. Glembotskii, Principles of the Physical Chemistry of Flotation Processes [in Russian], Nedra, Moscow (1980).

    Google Scholar 

  4. Heat Transfer in a Two-Phase Flow [in Russian], Énergiya, Moscow (1980).

  5. K. Sekoguchi et al., ISME,23, No. 184, 1625 (1980).

    Google Scholar 

  6. V. E. Serov et al., The Characteristics of a Two-Component Coolant-Gas Flow and Its Use for Cleaning Equipment of Atomic Power Stations and Accelerators [in Russian], Reports of the Gorki Polytechnical Institute No. 81, 100, 755, Gorki (1983).

Download references

Authors

Additional information

Translated from Atomnaya Énergiya, Vol. 57, No. 1, pp. 29–31, July, 1984.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Beznosov, A.V., Martynov, P.N., Orlov, S.Y. et al. Purification of the first circuit of nuclear power systems with a two-component coolant-gas flow. At Energy 57, 458–462 (1984). https://doi.org/10.1007/BF01135824

Download citation

  • Received:

  • Issue Date:

  • DOI: https://doi.org/10.1007/BF01135824

Keywords

Navigation