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Berkut Code Validation on Post-Reactor Studies of Irradiated Bn-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel

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Atomic Energy Aims and scope

An advanced version of the BERKUT-U/V2.1 code intended for modeling the behavior of fuel rods with oxide or nitride fuel in standard and emergency operating regimes of fast reactors with liquid-metal coolant is being developed at the Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAS), as part of the project Next-Generation Codes of Project Proryv (Breakthrough). The present work reports the results of the validation of an advanced version of the code based on post-reactor studies of BN-600 fuel rods (KETVS-1, -6) and BREST-OD-300 fuel rods (ETVS-5) with mixed uranium-plutonium nitride fuel, irradiated in the BN-600 reactor.

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References

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Authors and Affiliations

  1. Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAS), Moscow, Russia

    A. V. Boldyrev, A. V. Zadorozhnyi, V. D. Ozrin, V. I. Tarasov, I. O. Dolinskii & S. Yu. Chernov

Authors
  1. A. V. Boldyrev
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  2. A. V. Zadorozhnyi
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  3. V. D. Ozrin
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  4. V. I. Tarasov
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  5. I. O. Dolinskii
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  6. S. Yu. Chernov
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Corresponding author

Correspondence to A. V. Boldyrev.

Additional information

Translated from Atomnaya Énergiya, Vol. 127, No. 12, pp. 322–327, December, 2019.

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Boldyrev, A.V., Zadorozhnyi, A.V., Ozrin, V.D. et al. Berkut Code Validation on Post-Reactor Studies of Irradiated Bn-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel. At Energy 127, 356–361 (2020). https://doi.org/10.1007/s10512-020-00636-0

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  • DOI: https://doi.org/10.1007/s10512-020-00636-0

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