Advertisement

Atomic Energy

, Volume 122, Issue 3, pp 185–199 | Cite as

Investigations of Mixed Uranium-Plutonium Nitride Fuel in Project Breakthrough

  • A. F. Grachev
  • L. M. Zabud’ko
  • A. E. Glushenkov
  • Yu. A. Ivanov
  • G. A. Kireev
  • M. V. Skupov
  • I. F. Gil’mutdinov
  • P. I. Grin’
  • E. A. Zvir
  • F. N. Kryukov
  • O. N. Nikitin
Article

Mixed uranium-plutonium nitride fuel is seen as a promising fuel for fast reactors with a closed fuel cycle. A complex program of computational and experimental validation of this fuel up to 2020 has been developed within the scope of Project Breakthrough. Pre-reactor and post-reactor studies of mixed uranium-plutonium nitride fuel are part of this program. The basic research results obtained by the end of 2016 are examined.

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. 1.
    V. M. Troyanov, A. F. Grachev, L. M. Zabud’ko, and M. V. Skupov, “Prospects for using nitride fuel in fast reactors with a closed fuel cycle,” At. Energ., 117, No. 2, 69–75 (2014).CrossRefGoogle Scholar
  2. 2.
    V. M. Troyanov, A. F. Grachev, L. M. Zabud’ko, et al., “Program and certain results of pre-reactor studies of mixed uranium-plutonium nitride fuel for fast reactors,” At. Energ., 117, No. 4, 192–197 (2014).Google Scholar
  3. 3.
    V. M. Troyanov, A. F. Grachev, L. M. Zabud’ko, et al., “Program and certain results of reactor tests of mixed nitride fuel in fast reactors,” At. Energ., 118, No. 2, 75–79 (2015).CrossRefGoogle Scholar
  4. 4.
    Y. Arai, Y. Suzuki, T. Iwai, and T. Ohmichi, “Dependence of the thermal conductivity of (U, Pu)N on porosity and plutonium content,” J. Nucl. Mater., 195, 37–43 (1992).ADSCrossRefGoogle Scholar
  5. 5.
    Y. Suzuki and Y. Arai, “Thermophysical and thermodynamic properties of actinide mononitrides and their solid solutions,” J. Alloys Compounds, 271273, 577–582 (1998).Google Scholar
  6. 6.
    V. G. Baranov, A. V. Tenishev, R. S. Kuzmin, et al., “Thermal stability investigation technique for uranium nitride,” An. Nucl. Energy, 87, 784–792 (2016).CrossRefGoogle Scholar
  7. 7.
    M. Fromont, J. Lamontagne, M. Asou, and I. Aubrun, “Behavior of uranium-plutonium mixed nitride and carbide irradiated in Phenix,” in: Proc. GLOBAL-2005, Tsukuba, Japan, Oct. 9–13, 2005, p. 239.Google Scholar
  8. 8.
    B. D. Rogozkin, N. M. Stepennova, Yu. E. Fedorov, et al., “Results of tests of mixed mononitride fuel 45%Pu + 55%UN and 60%Pu + 40%UN in the BOR-60 reactor to burn up ~12% h.a.,” At. Energ., 110, No. 6, 332–346 (2011).Google Scholar
  9. 9.
    S. I. Porollo, A. M. Dvoriashin, Yu. V. Konobeev, and F. A Garner, “Microstructure and mechanical properties of ferritic/martensitic steel EP-823 after neutron irradiation to high doses in BOR-60,” J. Nucl. Mater., 329333, 314–318 (2004).Google Scholar

Copyright information

© Springer Science+Business Media, LLC 2017

Authors and Affiliations

  • A. F. Grachev
    • 1
  • L. M. Zabud’ko
    • 1
  • A. E. Glushenkov
    • 2
  • Yu. A. Ivanov
    • 2
  • G. A. Kireev
    • 2
  • M. V. Skupov
    • 2
  • I. F. Gil’mutdinov
    • 3
  • P. I. Grin’
    • 3
  • E. A. Zvir
    • 3
  • F. N. Kryukov
    • 3
  • O. N. Nikitin
    • 3
  1. 1.Innovation-Technology Center for Project Breakthrough (ITTsP Proryv)MoscowRussia
  2. 2.Bochvar High-Technology Research Institute for Inorganic Materials (VNIINM)MoscowRussia
  3. 3.State Science Center – Research Institute for Atomic Reactors (GNTs NIIAR)DimitrovgradRussia

Personalised recommendations