Skip to main content
SpringerLink
Log in

The degree of attainment of radiation equivalency of highly active waste and natural uranium in the fuel cycle of nuclear power plants in Russia

  • Articles
  • Published:
Atomic Energy Aims and scope

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

Access this article

Log in via an institution

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

Instant access to the full article PDF.

Institutional subscriptions

References

  1. E. O. Adamov, V. V. Orlov, V. S. Smirnov, et al., ‘The concept of extremely safe power reactors with liquid lead coding,’ Research and Development Institute of Power Engineering Report No. 050-367-3272 (1989).

  2. E. Adamov, V. Tsikunov, A. Filin, et al., ‘Liquid lead cooled fast reactor concept,’ in: Proc. Int. Topical Meeting ARS '94, Vol. 1, Pittsburgh, USA (1994), p. 502.

  3. ‘The degree of approximation to radiation equivalency in the existing fuel cycle of Russian power plants,’ Research and Development Institute of Power Engineering Report No. 050-396-4793 (1995).

  4. V. I. Zemlyanukhin, E. I. Il'enko, A. N. Kondrat'ev, et al., Radiochemical Reprocessing of the Nuclear Fuel of Atomic Power Plants [in Russian], Energoatomizdat, Moscow (1989).

    Google Scholar 

  5. Radiation Safety Standards NRB-76/87 [in Russian], Energoatomizdat, Moscow (1988).

  6. H. Umeci, H. Sacuma, K. Yshiguro, et al., ‘Near-field geological environment as an effective barrier against radionuclide transport,’ in: Int. Conf. on Nuclear Waste Management, Praha,1, 747 (1993).

    Google Scholar 

  7. A. V. Lopatkin and L. V. Tochenyi, ‘Development and improvement of the means of calculating and optimizing the nuclide composition of irradiated fuel,’ Research and Development Institute of Power Engineering Report No. 050-179-4197 (1992).

  8. A. V. Lopatkin and V. G. Muratov, ‘The UCDAS program.’ Research and Development Institute of Power Engineering Report No. 5.918 (1995).

  9. ENDF/B.VI. IAEA-NDS-100 (1993).

  10. MCNP-A. General Monte Carlo Code for Neutron, Photon and Electron Transport. LA 7396M (1991).

  11. S. V. Marin and N. E. Polikhovskaya, ‘A program for calculating the spatial-power distribution of neutrons in one-dimensional geometry, Preprint IAE-2832 (1977).

Download references

Authors
  1. E. O. Adamov
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. I. Kh. Ganev
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. A. V. Lopatkin
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. V. G. Muratov
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. V. V. Orlov
    View author publications

    You can also search for this author in PubMed Google Scholar

Additional information

Research and Development Institute of Power Engineering. Translated from Atomnaya Énergiya, Vol. 81, No. 6, pp. 403–409, December, 1996.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Adamov, E.O., Ganev, I.K., Lopatkin, A.V. et al. The degree of attainment of radiation equivalency of highly active waste and natural uranium in the fuel cycle of nuclear power plants in Russia. At Energy 81, 827–832 (1996). https://doi.org/10.1007/BF02419359

Download citation

  • Received:

  • Issue Date:

  • DOI: https://doi.org/10.1007/BF02419359

Keywords

Search

Navigation