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Atomic Energy

, Volume 125, Issue 6, pp 351–358 | Cite as

Gen-IV Reactor Systems Criteria Implementation in BN-1200

  • Yu. M. Ashurko
  • A. V. Gulevich
  • D. A. Klinov
  • B. A. Vasil’ev
  • A. V. Vasyaev
  • E. V. Marova
  • S. F. Shepelev
Article
  • 12 Downloads

The design of the BN-1200 sodium-cooled fast reactor is analyzed from the standpoint of its compliance with the criteria fitting the promising Gen-IV reactor facilities. The basic technical solutions adopted in the BN-1200 design making it possible to meet the requirements of consistent development of non-proliferation and safety, cost-effectiveness, and physical protection are described. The BN-1200 concept is evaluated on the basis of 26 criteria developed as part of the Generation IV international forum for the Gen-IV sodium-cooled fast reactor. The compliance of the safety requirements used in the development of the BN-1200 design with the design criteria for the Gen-IV sodium-cooled fast reactor developed as part of the Generation IV international forum is analyzed.

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Copyright information

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

Authors and Affiliations

  • Yu. M. Ashurko
    • 1
  • A. V. Gulevich
    • 1
  • D. A. Klinov
    • 1
  • B. A. Vasil’ev
    • 2
  • A. V. Vasyaev
    • 2
  • E. V. Marova
    • 2
  • S. F. Shepelev
    • 2
  1. 1.State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (IPPE)ObninskRussia
  2. 2.Afrikantov Experimental Design Bureau of Mechanical Engineering (OKBM Afrikantov)Nizhnii NovgorodRussia

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