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Key Outcomes of Comprehensive Computational and Experimental Validation of Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel for the BN-1200 and Brest Reactors

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The purpose of the program was to validate the resource dependability of fuel rods with mixed uranium-plutonium nitride fuel, the consistency of the reproduction of characteristics and quality required for this pilot technology for manufacturing pellets, fuel rods and experimental fuel assemblies for testing in the BOR-60 and BN-600 reactors, as well as optimization, in terms of the results of reactor testing, of the design and manufacturing technology of fuel rods for BN-1200 and BREST-OD-300. The article presents key results of the investigations: methods, codes, and criteria have been developed to validate the performance of fuel rods with nitride fuel, the necessary set of pre-reactor properties of mixed nitride fuel and cladding materials has been obtained, a cycle of reactor tests of experimental fuel rods in BOR-60 and BN-600 has been completed, the maximum fuel burnup 9% h.a., damaging dose 107.6 dpa, technical designs of fuel rods for initial loading have been developed, and the manufacturing technology for fuel and fuel rods has been developed and optimized.

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Authors and Affiliations

  1. JSC Proryv, Moscow, Russia

    E. O. Adamov, A. F. Grachev, L. M. Zabudko, E. V. Lachkanov & Yu. S. Mochalov

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

    A. V. Belyaeva & F. N. Kryukov

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

    Yu. A. Ivanov & M. V. Skupov

  4. State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (SSC IPPE), Obninsk, Russia

    E. E. Marinenko & S. I. Porollo

Authors
  1. E. O. Adamov
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  2. A. F. Grachev
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  3. L. M. Zabudko
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  4. E. V. Lachkanov
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  5. Yu. S. Mochalov
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  6. A. V. Belyaeva
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  7. F. N. Kryukov
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  8. Yu. A. Ivanov
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  9. M. V. Skupov
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  10. E. E. Marinenko
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  11. S. I. Porollo
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Corresponding author

Correspondence to A. F. Grachev.

Additional information

Translated from Atomnaya Énergiya, Vol. 131, No. 5, pp. 265–270, November, 2021.

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Adamov, E.O., Grachev, A.F., Zabudko, L.M. et al. Key Outcomes of Comprehensive Computational and Experimental Validation of Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel for the BN-1200 and Brest Reactors. At Energy 131, 268–273 (2022). https://doi.org/10.1007/s10512-022-00877-1

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  • DOI: https://doi.org/10.1007/s10512-022-00877-1

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