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Atomic Energy

, Volume 118, Issue 2, pp 96–100 | Cite as

Program and Results of Reactor Tests of Mixed Nitride Fuel for Fast Reactors

  • V. M. Troyanov
  • A. F. Grachev
  • L. M. Zabud’ko
  • M. V. Skupov
  • D. V. Zozulya
Article

In the Proryv project, mixed uranium-plutonium nitride fuel is to be used in the future nuclear power with fast reactors with sodium coolant (BN-1200) and with lead coolant (BREST). At present, experimental fuel elements and fuel assemblies with mixed nitride fuel are fabricated by means of a technology developed at the Bochvar All-Russia Research Institute for Inorganic Materials for testing in the BN-600 reactor and the MIR and BOR-60 research reactors. The program of reactor tests of the experimental fuel assemblies and some preliminary results of these tests are presented.

Keywords

Fuel Element Fuel Assembly Uranium Dioxide Fuel Kernel Experimental Fuel 
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 New York 2015

Authors and Affiliations

  • V. M. Troyanov
    • 1
  • A. F. Grachev
    • 1
  • L. M. Zabud’ko
    • 1
  • M. V. Skupov
    • 2
  • D. V. Zozulya
    • 3
  1. 1.Innovative Technological Center for the Proryv ProjectMoscowRussia
  2. 2.Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM)MoscowRussia
  3. 3.Siberian Chemical Combine (SKhK)SeverskRussia

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