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

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Atomic Energy Aims and scope

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.

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Authors and Affiliations

  1. Innovative Technological Center for the Proryv Project, Moscow, Russia

    V. M. Troyanov, A. F. Grachev & L. M. Zabud’ko

  2. Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM), Moscow, Russia

    M. V. Skupov

  3. Siberian Chemical Combine (SKhK), Seversk, Russia

    D. V. Zozulya

Authors
  1. V. M. Troyanov
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  2. A. F. Grachev
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  3. L. M. Zabud’ko
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  4. M. V. Skupov
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  5. D. V. Zozulya
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Additional information

Translated from Atomnaya Énergiya, Vol. 118, No. 2, pp. 75–79, February, 2015.

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Troyanov, V.M., Grachev, A.F., Zabud’ko, L.M. et al. Program and Results of Reactor Tests of Mixed Nitride Fuel for Fast Reactors. At Energy 118, 96–100 (2015). https://doi.org/10.1007/s10512-015-9962-0

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  • DOI: https://doi.org/10.1007/s10512-015-9962-0

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