Skip to main content
Log in

Development of New Construction Materials for Innovative Reactor Installation Designs

  • Published:
Atomic Energy Aims and scope

Different stages of the development of new construction materials at NIKIET for innovative designs of reactor installations are analyzed. Justification is given for the use of large-sized intermediate products made of a nickel-based alloy (KhN55MVTs (ChS57) grade) for vessel elements and intermediate products made of molybdenum alloy of the TSM-7 type for the core elements of a high-temperature reactor installation. The next-generation corrosion-resistant steel EP302M-Sh has been developed and introduced for the BREST-OD-300 steam generator, and the production of extra-long pipes made from this steel has been mastered. Research is being performed on a new corrosion-resistant lean-alloyed steel with improved manufacturability metrics (EP750M grade).

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

Access this article

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

Instant access to the full article PDF.

Institutional subscriptions

Similar content being viewed by others

References

  1. V. N. Elkin, A. A. Komarova, O. V. Goslavskii, et al., “Diffusion welding of KhN55MVTs alloy by hot isostatic pressing,” in: Annual Report of NIKIET-2016 (2016), pp. 212–213.

  2. O. V. Goslavskii, A. B. Korostelev, M. I. Alishin, et al., “Improved technology for the manufacture of industrial blanks from alloy make KhN55MVTs-ID (ChS57-ID),” ibid. (2017), pp. 221–222.

  3. M. I. Alishin, R. Yu. Malinin, B. S. Rodchenkov, et al., “Mechanical properties of alloy TSM-7S,” ibid. (2015), pp. 210–212.

  4. I. V. Vershinin and A. Yu. Lukashevich, “Investigation of the effect of thermal annealing on the metal structure of semi-finished products made from the TSM-7S molybdenum alloy,” ibid., pp. 212–213.

  5. Yu. G. Dragunov, V. V. Lemekhov, V. S. Smirnov, and N. G. Chernetsov, “Technical solutions and stages of development of the BREST-OD-300 reactor plant,” At. Energ., 113, No. 1, 58–64 (2012).

    Google Scholar 

  6. Yu. G. Dragunov, V. V. Lemekhov, and V. S. Smirnov, “Lead-cooled fast neutron reactor (BREST),” in: 3rd Int. Sci. Techn. Conf. on Innovative Projects and Technologies of Nuclear Energy (MNTK-2014), NIKIET, Moscow (2014), Vol. 1, pp. 94–102.

  7. N. S. Krestnikov, A. B. Korostelev, and O. V. Novichkova, “Development and implementation of a new generation of corrosion-resistant steel for the implementation of innovative projects in large-scale power engineering,” Probl. Mashinostr. Avtomatiz., No. 2, 112–115 (2016).

  8. N. S. Krestnikov, A. B. Korostelev, and O. V. Novichkova, “Corrosion-resistant steel of a new generation for steam generators of fast reactors with lead coolant,” in: Annual Report of NIKIET-2016 (2016), p. 202.

  9. A. B. Korostelev, N. S. Krestnikov, and O. V. Novichkova, “Development and implementation of new-generation corrosion-resistant steel for realization of innovative reactor installations of large-scale energetics,” in: 4th Int. Sci. Techn. Conf. on Innovative Projects and Technologies of Nuclear Energy (MNTK-2016), NIKIET, Moscow (2016), Vol. 1, pp. 270–273.

  10. A. B. Korostelev, N. S. Krestnikov, V. V. Lemekhov, and O. V. Novichkova, “New-generation steel for heat exchangers of reactor installations with lead coolant,” Vopr. At. Nauki Tekhn. Ser. Obesp. Bezopasn. AES, No. 36, 92–94 (2016).

  11. G. M. Kalinin, A. B. Korostelev, and Yu. I. Trifonov, “Basis of structural stability of austenitic class steels after prolonged thermal soaking,” in: Annual Report NIKIET-2018 (2018), pp. 165–167.

  12. A. B. Korostelev, V. Ya. Abramov, and V. N. Belous, “Evaluation of stainless steels for their resistance to intergranular corrosion,” Nucl. Mater., 233–237, Pt. II, 1361–1363 (1996).

  13. L. V. Pisarevskii, A. B. Korostelev, A. A. Lipatov, et al., “Local corrosion of austenitic steels and alloys for heat exchange tubes of steam generations in AES,” Chern. Metallurg., No. 2, 227–241 (2019).

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to A. B. Korostelev.

Additional information

Translated from Atomnaya Énergiya, Vol. 129, pp. 233–237, October, 2020.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Korostelev, A.B., Evropin, S.V., Derzhavin, A.G. et al. Development of New Construction Materials for Innovative Reactor Installation Designs. At Energy 129, 237–241 (2021). https://doi.org/10.1007/s10512-021-00741-8

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-021-00741-8

Navigation