Skip to main content
SpringerLink
Log in

Development of Radiation Porosity in Austenitic EK164-ID c.d. Steel Irradiated at 715–815 K to Damage Doses of 72–92 dpa

  • Published:
Russian Metallurgy (Metally) Aims and scope

Abstract

Microstructural examination of EK164-ID c.d. steel samples cut from a fuel element cladding is carried out after its operation in a reactor untill the maximum damaging dose of 96 dpa. The critical diameter of void nuclei is estimated from void size distribution histograms. The critical void nucleus diameter is shown to increase with the porosity, which blocks the transition of helium–vacancy nuclei into the class of vacancy voids. This finding, together with the histograms of void size distribution, indicates that the final stage of transient swelling has been reached when new voids are not formed. The growth of voids and their coalescence are responsible for the swelling increasing. Microstructural findings are used to describe the evolution of the radiation porosity in EK164-ID c.d. steel samples at this stage. The remaining service life of fuel elements is estimated using the 15% swelling criterion.

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

Fig. 1.
Fig. 2.
Fig. 3.
Fig. 4.
Fig. 5.
Fig. 6.

Similar content being viewed by others

REFERENCES

  1. F. A. Garner, M. B. Toloczko and B. N. Sencer, “Comparison of swelling and irradiation creep behavior of fcc-austenitic/martensitic alloys at high neutron exposure,” Nucl. Mater. 276, 123–142 (2000).

    Article  CAS  Google Scholar 

  2. N. M. Mitrofanova, A. V. Tselishchev, V. S. Ageev, et al., “Structural materials for fuel cladding and subassembly wrappers of the BN 600 Reactor,” Izv. Vyssh. Uchebn. Zaved., Yad. Energ. No. 1, 211–223 (2011).

    Google Scholar 

  3. S. V. Bogatov and M. G. Kireev, “Methods and results for calculating the temperatures of the fuel in BN-600 reactor fuel elements,” Izv. Vyssh. Uchebn. Zaved., Yad. Energ. No. 2, 127–135 (2009).

    Google Scholar 

  4. P. Hirsch, A. Howie, R. Nicholson, D. Pashley, and M. Whelan, Electron Microscopy of Thin Crystals (Mir, Moscow, 1968).

  5. B. B. Glasgow, A. Si-Ahmed, W. G. Wolfer, and F. A. Garner, “Helium bubble formation and swelling in metals,” Nucl. Mater. 103–104, 981–986 (1981).

  6. A. G. Zaluzhnyi, Yu. N. Sokurskii, and V. N. Tebus, Helium in Reactor Materials (Energoatomizdat, Moscow, 1988).

    Google Scholar 

  7. A. V. Kozlov, I.A. Portnykh, A.I. Blokhin, et al., “The critical pore diameter in austenitic ChS-68 steel as a function of the temperature of neutron irradiation in the model of helium vacancy bubbles formation,” Fiz. Khim. Obrab. Mater., No. 1, 16–22 (2012).

  8. A. V. Kozlov, “Radiation defects in austenitic steels during neutron irradiation and their effect on physical and mechanical properties,” Izv. Vyssh. Uchebn. Zaved., Yad. Energ. No. 1, 196–210 (2011).

    Google Scholar 

  9. A. V. Kozlov and I. A. Portnykh, “Vacancy void growth rate as a function on the neutron irradiation parameters at the initial stage of transient swelling,” Russ. Metall. (Metally), No. 3, 261–267 (2019).

  10. L. K. Mansur, “Theory and experimental background on dimensional changes in irradiated alloys,” Nucl. Mater. 216, 97–123 (1994).

    Article  CAS  Google Scholar 

  11. A. M. Parshin, I. M. Neklyudov, and N. V. Kamyshanchenko, Physics of Radiation Phenomena and Radiation Materials Science (Belgorod Gos. Univ., Belgorod, 1998).

    Google Scholar 

  12. V. N. Voevodin, “Structural materials of nuclear power engineering—challenge of 21st century,” Vopr. At. Nauki Tekh., Ser. Fiz. Radiats. Povrezhd. Radiats. Materialoved. 90 (3), 10–22 (2007).

    Google Scholar 

  13. C. H. Woo, B. N. Singh, and A. A. Semenov, “Recent advances in the understanding of damage production and its consequences on void swelling, irradiation creep and growth,” J. Nucl. Mater., 239, 7–23 (1996).

    Article  CAS  Google Scholar 

  14. A. R. Isimbaev, A. V. Kozlov, and I. A. Portnykh, “Effect of radiation porosity parameters on the concentration of point self-defects in austenitic steels,” in Proceedings of 13th International Ural Seminar on Radiation Physics of Metals and Alloys (Kyshtym, 2019), pp. 8–9.

  15. M. V. Bakanov, V. V. Mal’tsev, N. N. Oshkanov, V. V. Chuev, “Main results of performance monitoring of fuel elements with austenitic steel shells of the new generation,” Izv. Vyssh. Uchebn. Zaved., Yad. Energ. No. 1, 187–195 (2011).

    Google Scholar 

Download references

Author information

Authors and Affiliations

  1. AO Institute of Reactor Materials, Zarechnyi, Sverdlovsk oblast, Russia

    I. A. Portnykh, A. V. Kozlov & A. R. Isinbaev

Authors
  1. I. A. Portnykh
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. A. V. Kozlov
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. A. R. Isinbaev
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding authors

Correspondence to I. A. Portnykh or A. V. Kozlov.

Additional information

Translated by T. Gapontseva

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Portnykh, I.A., Kozlov, A.V. & Isinbaev, A.R. Development of Radiation Porosity in Austenitic EK164-ID c.d. Steel Irradiated at 715–815 K to Damage Doses of 72–92 dpa. Russ. Metall. 2021, 290–296 (2021). https://doi.org/10.1134/S0036029521030113

Download citation

  • Received:

  • Revised:

  • Accepted:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1134/S0036029521030113

Keywords:

Search

Navigation