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Analysis of Experimental Data on Gas Release and Swelling of Uranium Mononitride Fuel Irradiated in the BR-10 Reactor

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Atomic Energy Aims and scope

The results of an investigation of gas release and swelling of uranium mononitride fuel after irradiation in standard and experimental fuel assemblies in the BR-10 reactor in the burnup range 3.4–8.4% h.a. are presented and analyzed. The results obtained were used to verify the fuel code DRAKON.

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Authors and Affiliations

  1. State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI), Obninsk, Russia

    S. I. Porollo, S. N. Ivanov & E. E. Marinenko

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

    L. M. Zabud’ko

Authors
  1. S. I. Porollo
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  2. S. N. Ivanov
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  3. E. E. Marinenko
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  4. L. M. Zabud’ko
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Translated from Atomnaya Energiya, Vol. 121, No. 6, pp. 326–332, December, 2016.

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Porollo, S.I., Ivanov, S.N., Marinenko, E.E. et al. Analysis of Experimental Data on Gas Release and Swelling of Uranium Mononitride Fuel Irradiated in the BR-10 Reactor . At Energy 121, 415–423 (2017). https://doi.org/10.1007/s10512-017-0221-4

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  • DOI: https://doi.org/10.1007/s10512-017-0221-4

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