Atomic Energy

, Volume 125, Issue 3, pp 185–193 | Cite as

Corrosion Damage and Mechanical Properties of BR-10 Reactor Fuel-Rod Cladding with Mononitride Uranium Fuel

  • S. I. Porollo
  • S. N. Ivanov

The results of investigations of the corrosion damage and short-time mechanical properties of the fuel-rod cladding and standard and experimental fuel assemblies of the BR-10 reactor with uranium mononitride fuel are presented. It is shown that after irradiation the corrosion depth in the fuel rods of the BR-10 reactor reached 75 μm for the standard and 180 μm for the experimental FA. Degradation of the mechanical properties of fuel-rod cladding also occurred. The corrosion and degradation of the mechanical properties of the cladding of BR-10 reactor fuel rods should be attributed primarily to the high level of impurities in the initial fuel.


Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.


  1. 1.
    S. I. Porollo, S. N. Ivanov, E. E. Marinenko, and L. M. Zabudko, “Analysis of experimental data on gas evolution and swelling of mononitride uranium fuel irradiated in a BR-10 reactor,” At. Energ., 121, No. 6, 326–332 (2016).Google Scholar
  2. 2.
    E. O. Adam, R. M. Aleksakhin, L. A. Bolshov, et al., “Project Breakthrough is a technological foundation for largescale nuclear energy,” Izv. Akad. Nauk. Energetika, No. 1, 5–12 (2015).Google Scholar
  3. 3.
    L. M. Zabudko, L. I. Mamaev, and A. A. Trufanov, “Analysis of the calculated and experimental data in order to determine possible causes of depressurization of fuel elements with the nitride fuel of the BR-10 reactor,” in: 7th Russ. Conf. on Reactor Materials Science (2004), Vol. 2, Pt. 2, pp. 176–186.Google Scholar
  4. 4.
    L. M. Zabudko, A. A. Kamaev, L. I. Mamaev, et al., “Nitride fuel for advanced sodium reactors,” in: Proc. Int. Conf. Global-2003, pp. 1679–1685.Google Scholar
  5. 5.
    D. Fee and C. Johnson, “Fuel-cladding chemical interaction in uranium-plutonium oxide fast reactor fuel pins,” J. Nucl. Mater., 96, 80–104 (1981).ADSCrossRefGoogle Scholar
  6. 6.
    V. M. Poplavskoi, Handbook of the Properties of Materials for Advanced Reactor Technologies, Vol. 5, Properties of Reactor Steels and Alloys, IzdAT, Moscow (2014).Google Scholar

Copyright information

© Springer Science+Business Media, LLC, part of Springer Nature 2018

Authors and Affiliations

  • S. I. Porollo
    • 1
  • S. N. Ivanov
    • 1
  1. 1.State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (IPPE)ObninskRussia

Personalised recommendations