Atomic Energy

, Volume 123, Issue 5, pp 302–306 | Cite as

Computational and Experimental Validation of the Serviceability of RBMK Core Elements Under Graphite Stack Distortion Conditions

  • S. V. Evropin
  • A. P. Rakhmanov
  • E. V. Churakova
  • I. M. Baranov
  • S. M. Usov
Article
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Computational and experimental validation of the serviceability of zirconium channels in the reactor core according to strength criteria was conducted in order to ensure safe operation of the RBMK reactor facility under graphite stack deformation conditions. A complex of computational and experimental studies confirmed that the requirements of the operative federal norms and regulations for objects using nuclear power are met

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References

  1. 1.
    PNAE G-7-002–86, Computational Norms for the Strength of Equipment and Pipelines in Nuclear Power Facilities, Energoatomizdat, Moscow (1989).Google Scholar
  2. 2.
    PNAE G-7-008–89, Regulations for Arrangement and Safe Operation of Equipment and Pipelines of in Nuclear Power Plants, Energoatomizdat, Moscow (1990).Google Scholar
  3. 3.
    PNAE G-7-018–89, Safety Guide. Unified Methods of Monitoring the Primary Materials (intermediate products), Weld Joints, and Surfacing of Equipment and Piping in NPP. Capillary Inspection, Energoatomizdat, Moscow (1990).Google Scholar

Copyright information

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

Authors and Affiliations

  • S. V. Evropin
    • 1
  • A. P. Rakhmanov
    • 1
  • E. V. Churakova
    • 1
  • I. M. Baranov
    • 1
  • S. M. Usov
    • 1
  1. 1.Dollezhal Research and Development Institute of Power Engineering (NIKIET)MoscowRussia

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