Advertisement

Atomic Energy

, Volume 126, Issue 1, pp 21–28 | Cite as

Concept Selection and Neutronic Characteristics of Nuclear Icebreaker Cores

  • E. A. Dvoinishnikov
  • V. I. Makarov
  • A. G. Promokhov
  • O. B. Samoilov
  • O. A. Morozov
  • V. I. Alekseev
  • V. Yu. Silaev
Article

The developmental history of the series-produced core for nuclear icebreakers and its conceptual and structural designs and the computational-methodological base of the physical design are presented. The fundamental differences from VVER-type power reactor cores, which are due to the specific operating conditions of ice breakers, are discussed. Measurements of the basic neutronic characteristics of a series-produced icebreaker core are presented and compared with calculations performed with the tested software system VKN-02. Experimental data confirm that the accuracy of the VKN-02 system in calculating the neutronic characteristics determining nuclear safety and the thermal engineering reliability of an icebreaker core is acceptable.

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. 1.
    O. B. Samoilov, D. G. Preobrazhenskii, O. A. Morozov, et al., “Operational results and operating conditions of Icebreaker cores,” in: Abstr. 9th Russ. Conf. on Reactor Materials Engineering, NIIAR, Dimitrovgrad, Sept. 14, 2009, pp. 68–70.Google Scholar
  2. 2.
    D. L. Zverev, O. B. Samoilov, D. G. Preobrazhenskii, et al., “Experience in operating the cores of operating nuclear icebreakers,” Sudostroenie, No. 4, 34 (2017).Google Scholar
  3. 3.
    A. V. Vatulin, “State and prospects for the development dispersion fuel rods for water moderated and cooled reactors of different types,” in: VNIINM50 Years, Moscow (1999), Vol. 3, pp. 90–99.Google Scholar
  4. 4.
    G. V. Kulakov, A. V. Vitulin, S. A. Ershov, et al., “Experience and prospects for development of materials and fuel rods for transport reactors and small nuclear power plants,” At. Energ., 115, No. 5, 243–249 (2015).Google Scholar
  5. 5.
    VKN-02 Software System, NTTs YaRB Rostekhnadzora, Moscow (2003).Google Scholar
  6. 6.
    D. Bell and S. Glasstone, Theory of Nuclear Reactors, Atomizdat, Moscow (1974).Google Scholar
  7. 7.
    G. G. Bartolomei, G. A. Bat’, V. D. Baibakov, and M. S. Altukhov, Fundamentals of the Theory of the Calculation of Nuclear Power Reactors, Energoizdat, Moscow (1982).Google Scholar
  8. 8.
    A. D. Galanin, Theory of Heterogeneous Reactors, Atomizdat, Moscow (1971).Google Scholar

Copyright information

© Springer Science+Business Media, LLC, part of Springer Nature 2019

Authors and Affiliations

  • E. A. Dvoinishnikov
    • 1
  • V. I. Makarov
    • 1
  • A. G. Promokhov
    • 1
  • O. B. Samoilov
    • 2
  • O. A. Morozov
    • 2
  • V. I. Alekseev
    • 2
  • V. Yu. Silaev
    • 2
  1. 1.National Research Center Kurchatov InstituteMoscowRussia
  2. 2.Afrikantov Experimental Design Bureau of Mechanical Engineering (OKBM Afrikantov)Nizhnii NovgorodRussia

Personalised recommendations