Skip to main content
SpringerLink
Log in

An analysis of the nuclear safety of the VVÉR-1000 storage tank when the collant density is reduced

  • 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. Safety Rules for the Storage and Transport of Nuclear Fuel in Nuclear Power Plants (PB-YaT-KhT-90). (PNAÉ G-14-029-91) [in Russian], Gospromatomnadzor Rossii, Moscow (1991).

  2. G. Ya. Andrianov, V. S. Ionov, Yu. A. Kraynov, et al., "Calculation and experimental data comparison for critical experiments at core with hexagonal water ring," in: Proc. Intern. Top. Meeting on VVÉR Safety, Prague, Czech Republic, September 21–23 (1995), pp. 223–226.

  3. E. A. Gomin and L. V. Maiorov, "The MCU-RFFI Monte Carlo code for reactor design applications," in: Proc. Intern. Conf. on Math. and Comp., Reactor Physics and Envir. Anal., Portland, Oregon (1995).

    Google Scholar 

  4. E. A. Gomin, M. I. Gurevich, L. V. Maiorov, and S. V. Marin, Description of the Application and Instructions for the User of the MCU-RFFI Monte Carlo Software for Calculating the Neutron Characteristics of Nuclear Reactors [in Russian], Preprint IAE-5837/5 (1994).

  5. P. A. Bolobov and L. K. Shishkov, "A program for designing a two-dimensional reactor in the diffusion-group approximation," Leningrad Institute of Nuclear Physics Data Center Bulletin, No. 9, Leningrad (1981).

  6. L. P. Abagyan, N. O. Bazazyants, I. I. Bondarenko, and M. N. Nikolaev, Group Constants for Designing Nuclear Reactors [in Russian], Atomizdat, Moscow (1964).

    Google Scholar 

  7. L. P. Abagyan, N. I. Alekseev, V. I. Bryzgalov, et al., The MCU Monte Carlo Program for Calculating the Neutron Characteristics of Nuclear Reactors. Verification [in Russian], Preprint IAE-5741/5 (1994).

  8. N. I. Alekseev, V. I. Bryzgalov, E. A. Gomin, et al., Verification of the MCU-RFFI Program as Applied to Water-Water Reactors [in Russian], Preprint IAE-5932/5 (1995).

  9. M. I. Gurevich and N. I. Alekseev, The MCU Program for a Monte Carlo Calculation of the Neutron Characteristics of Nuclear Reactors. Universal Geometrical Model [in Russian], Preprint IAE-5912/5 (1995).

  10. N. I. Alekseev, V. V. Veretenov, and M. I. Gurevich, The MCU Program for a Monte Carlo Calculation of the Neutron Characteristics of Nuclear Reactors. The SCG-8 Geometrical Module [in Russian], Preprint IAE-5945/5 (1995).

  11. V. D. Sidorenko, "The KASSETA program," Proceedings of the Eleventh VMK Symposium on VVÉR Physics, Bucharest (1997).

Download references

Authors
  1. N. I. Alekseev
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. G. Ya. Andrianov
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. P. A. Bolobov
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. M. I. Gurevich
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. V. S. Ionov
    View author publications

    You can also search for this author in PubMed Google Scholar

Additional information

Kurchatov Institute, Russian Science Center. Translated from Atomnaya Énergiya, Vol. 81, No. 4, pp. 243–249, October, 1996.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Alekseev, N.I., Andrianov, G.Y., Bolobov, P.A. et al. An analysis of the nuclear safety of the VVÉR-1000 storage tank when the collant density is reduced. At Energy 81, 683–689 (1996). https://doi.org/10.1007/BF02407065

Download citation

  • Received:

  • Issue Date:

  • DOI: https://doi.org/10.1007/BF02407065

Keywords

Search

Navigation