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Investigation of the corrosion resistance of fuel micropellet cladding made of silicon carbide and pyrolytic carbon for the operating conditions of light-water reactors in nuclear power plants

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Abstract

The results of experimental and theoretical investigations of the corrosion of outer protective coatings, made of silicon carbide and pyrolytic carbon, of fuel microspherules in high-pressure water and water vapor in the range 350–950°C are presented. The tests lasted for times ranging from 300 to 11800 h were conducted for the operating conditions of light-water reactors.

A comparative estimate is given of the corrosion resistance of two types of coatings. The temperature-time curves, which make it possible to determine by interpolation and extrapolation the degree of corrosion of the protective coatings for different operating regimes of the reactor, are obtained.

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Authors and Affiliations

  1. All-Russia Research Institute of Automatic Machines, Russia

    G. A. Filippov, E. I. Grishanin, M. V. Konditerov, V. P. Mastyukin, V. I. Mel’kin, V. M. Trubachev, L. N. Fal’kovskii & B. I. Fonarev

  2. Russian Science Center Kurchatov Institute, Russia

    G. V. Momot

Authors
  1. G. A. Filippov
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  2. E. I. Grishanin
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  3. M. V. Konditerov
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  4. V. P. Mastyukin
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  5. V. I. Mel’kin
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  6. V. M. Trubachev
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  7. L. N. Fal’kovskii
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  8. B. I. Fonarev
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  9. G. V. Momot
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Translated from Atomnaya Énergiya, Vol. 101, No. 4, pp. 270–278, October, 2006.

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Filippov, G.A., Grishanin, E.I., Konditerov, M.V. et al. Investigation of the corrosion resistance of fuel micropellet cladding made of silicon carbide and pyrolytic carbon for the operating conditions of light-water reactors in nuclear power plants. At Energy 101, 722–729 (2006). https://doi.org/10.1007/s10512-006-0159-4

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  • DOI: https://doi.org/10.1007/s10512-006-0159-4

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