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Modeling of 14C Diffusion from the Core of the Decommissioned ad Reactor

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Atomic Energy Aims and scope

A mathematical model of the diffusion of radionuclides through engineered safety barriers is developed for 14C in order to determine the long-term safety conditions and characteristics of a decommissioned commercial uranium-graphite reactor. Dry and wet mixtures and concrete are used as the barrier materials. Diffusion is studied as the dominant mechanism for the transport of the radionuclides. The 14C concentration at the boundary between the radwaste storage site and the environment is determined computationally and the effect of the modeling conditions on the specific activity of the radionuclide is analyzed. The decomposition sequence of the safety barriers for which the 14C concentration is much lower than the admissible value is determined.

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Authors and Affiliations

  1. Mining and Chemical Combine, Zheleznogorsk, Russia

    M. V. Antonenko & D. O. Chubreev

  2. National Research Tomsk Polytechnic University, Tomsk, Russia

    G. V. Kuznetsov

Authors
  1. M. V. Antonenko
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  2. D. O. Chubreev
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  3. G. V. Kuznetsov
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Additional information

Translated from Atomnaya Énergiya, Vol. 118, No. 5, pp. 278–281, May, 2015.

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Antonenko, M.V., Chubreev, D.O. & Kuznetsov, G.V. Modeling of 14C Diffusion from the Core of the Decommissioned ad Reactor. At Energy 118, 346–350 (2015). https://doi.org/10.1007/s10512-015-0005-7

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  • DOI: https://doi.org/10.1007/s10512-015-0005-7

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