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Results of Studies of BN-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel and ChS68-ID c.d. Steel Cladding

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Reactor tests in BN-600 and post-reactor studies of experimental FA of fuel rods with mixed nitride fuel and different cladding are being conducted in Project Breakthrough. In the present article, the irradiation parameters of fuel rods with mixed nitride fuel and cladding made from ChS68-ID c.d. austenitic steel are presented: maximum linear power density 38.3 kW/m, maximum fuel burnup 7.5% h.a., and maximum damage dose 73.6 dpa. No depressurization of the fuel elements was recorded. The results of post-reactor examination (PIE) of the irradiated fuel rods are presented – swelling, gas release from fuel, and mechanical and corrosion characteristics of the cladding.

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Authors and Affiliations

  1. Innovation-Technology Center for Project Breakthrough (ITTsP Proryv), Moscow, Russia

    A. F. Grachev & L. M. Zabud’ko

  2. Bochvar High-Technology Research Institute of Inorganic Materials (VNIINM), Moscow, Russia

    Yu. A. Ivanov & M. V. Skupov

  3. State Science Center of the Russian Federation – Research Institute of Atomic Reactors (SSC RIAR), Dimitrovgrad, Russia

    E. A. Zvir, F. N. Kryukov & O. N. Nikitin

  4. Leipunskii Institute of Physics and Power Engineering (IPPE), Obninsk, Russia

    E. E. Marinenko & S. I. Porollo

Authors
  1. A. F. Grachev
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  2. L. M. Zabud’ko
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  3. Yu. A. Ivanov
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  4. M. V. Skupov
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  5. E. A. Zvir
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  6. F. N. Kryukov
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  7. O. N. Nikitin
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  8. E. E. Marinenko
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  9. S. I. Porollo
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Corresponding author

Correspondence to A. F. Grachev.

Additional information

Translated from Atomnaya Énergiya, Vol. 126, No. 3, pp. 160–166, March, 2019.

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Grachev, A.F., Zabud’ko, L.M., Ivanov, Y.A. et al. Results of Studies of BN-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel and ChS68-ID c.d. Steel Cladding. At Energy 126, 182–190 (2019). https://doi.org/10.1007/s10512-019-00534-0

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  • DOI: https://doi.org/10.1007/s10512-019-00534-0

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