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Atomic Energy

, Volume 103, Issue 1, pp 501–508 | Cite as

Brest reactor and plant-site nuclear fuel cycle

  • A. G. Glazov
  • V. N. Leonov
  • V. V. Orlov
  • A. G. Sila-Novitskii
  • V. S. Smirnov
  • A. I. Filin
  • V. S. Tsikunov
Article

Abstract

The fundamental design of BREST-OD-300 and BREST-1200 reactors is presented. It is shown that it is necessary to develop nuclear energy complexes based on the BREST nuclear system. The stages, the status of scientific research and development work over the entire nuclear power complex, and the results of an expert analysis of the BREST-OD-300 design are presented.

Keywords

Plutonium Fuel Element Fuel Assembly Steam Generator Nuclear Fuel Cycle 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Copyright information

© Springer Science+Business Media, Inc. 2007

Authors and Affiliations

  • A. G. Glazov
    • 1
  • V. N. Leonov
    • 1
  • V. V. Orlov
    • 1
  • A. G. Sila-Novitskii
    • 1
  • V. S. Smirnov
    • 1
  • A. I. Filin
    • 1
  • V. S. Tsikunov
    • 1
  1. 1.N. A. Dollezhal Research and Design Institute of Electrical TechnologyRussia

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