Search Results - "Antonenko, V. M."

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  1. 1

    Electrochemical treatment of irradiated nuclear graphite by Bespala, E.V., Antonenko, M.V., Chubreev, D.O., Leonov, A.V., Novoselov, I. Yu, Pavlenko, A.P., Kotov, V.N.

    Published in Journal of nuclear materials (01-12-2019)
    “…The paper is dedicated to the issues of accumulation of irradiated reactor graphite and possible options for handling it. There are described the advantages of…”
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    Journal Article
  2. 2

    Combustion of a Dust/Gas Mixture Consisting of Particles of Irradiated Nuclear Graphite by Antonenko, M. V., Chubreev, D. O., Bespala, E. V., Leonov, A. V., Pavlenko, A. P.

    “…The paper describes the problem of the formation of dust/gas mixtures during the work related to the dismantling of graphite stack during the decommissioning…”
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    Journal Article
  3. 3

    Corrosion Effect on Concrete Barrier Life of a Decommissioned AD Reactor by Antonenko, M. V., Chubreev, D. O., Kuznetsov, G. V.

    Published in Atomic energy (New York, N.Y.) (01-11-2016)
    “…A mathematical model of diffusion of calcium hydroxide in the system concrete barrier–ambient environment was developed to determine the influence of corrosion…”
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    Journal Article
  4. 4

    GIS MODELING OF FOREST COVER ON THE BASIS OF AIRBORNE LASER SCANNING by Rizaev, I. G., Pogorelov, A. V., Antonenko, M. V., Kuzyakina, M. V.

    Published in InterCarto. InterGIS (01-01-2015)
    “…The canopy height models (CHM) derived on the basis of laser scanning technology become popular due to the several important factors. On the one hand, it…”
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    Journal Article
  5. 5

    Study of irradiated graphite-bakelite paste by Bespala, E.V., Antonenko, M.V., Bespala, Yu.R., Kotov, V.N., Novoselov, I.Yu

    Published in Nuclear materials and energy (01-06-2021)
    “…•The study of irradiated graphite-bakelite paste from a uranium-graphite reactor was carried out for the first time.•The radionuclide composition and the rate…”
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    Journal Article
  6. 6

    Modeling of 14C Diffusion from the Core of the Decommissioned ad Reactor by Antonenko, M. V., Chubreev, D. O., Kuznetsov, G. V.

    Published in Atomic energy (New York, N.Y.) (01-09-2015)
    “…A mathematical model of the diffusion of radionuclides through engineered safety barriers is developed for 14 C in order to determine the long-term safety…”
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    Journal Article
  7. 7

    Modeling of ^sup 14^C Diffusion from the Core of the Decommissioned ad Reactor by Antonenko, M V, Chubreev, D O, Kuznetsov, G V

    Published in Atomic energy (New York, N.Y.) (01-09-2015)
    “…A mathematical model of the diffusion of radionuclides through engineered safety barriers is developed for ^sup 14^C in order to determine the long-term safety…”
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    Journal Article
  8. 8

    Modeling of super(14)C Diffusion from the Core of the Decommissioned ad Reactor by Antonenko, M V, Chubreev, DO, Kuznetsov, G V

    Published in Atomic energy (New York, N.Y.) (01-09-2015)
    “…A mathematical model of the diffusion of radionuclides through engineered safety barriers is developed for super(14)C in order to determine the long-term…”
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    Journal Article
  9. 9

    Modeling of [sup.14]C diffusion from the core of the decommissioned ad reactor by Antonenko, M.V, Chubreev, D.O, Kuznetsov, G.V

    Published in Atomic energy (New York, N.Y.) (01-09-2015)
    “…A mathematical model of the diffusion of radionuclides through engineered safety barriers is developed for [sup.14]C in order to determine the long-term safety…”
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    Journal Article
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