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Computer modeling of the behavior of flue-element casings of water-moderated water-cooled power reactors under accident conditions with azimuthal temperature inhomogeneities

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Literature Cited

  1. V. Solyany et al., “High-temperature oxidation and deformation of Zr 1% Nb alloy claddings of WER fules” in: OECD-NEA-CSNI/IAEA Specialists' Meeting on Water Reactor Fuel Safety and Fission Product Release in Off-Normal and Accident Conditions, Denmark, May, 1983, Vienna: IAEA, pp. 163–174.

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  2. J. Kensenhoff et al., “Development and application of an asymmetric model to describe the fuel rod behavior during LOCA,” in: OECD-NEA-CSNI/IAEA Specialists' Meeting on Water Reactor Fuel Safety and Fission Product Release in Off-Normal and Accident Conditions, Denmark, May 1983. Vienna: IAEA, pp. 141–147.

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  3. P. Jackson and I. Palmer, “The influence of fuel pellet fragmentation on predicted azimuthal temperature variations in ballooning cladding,” in: OECD-NEA-CSNI/IAEA Specialists' Meeting on Water Reactor Fuel Safety and Fission Product Release in Off-Normal and Accident Conditions, Denmark, May 1983. Vienna: IAEA, pp. 133–140.

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  4. V. S. Chirkin, Thermophysical Properties of Materials of Nuclear Technology [in Russian], Atomizdat, Moscow (1968).

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Authors
  1. V. I. Solyanyi
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  2. L. N. Andreeva-Andrievskaya
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  3. V. V. Fedotov
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Additional information

Translated from Atomnaya Énergiya, Vol. 63, No. 1, pp. 8–11, July, 1987.

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Solyanyi, V.I., Andreeva-Andrievskaya, L.N. & Fedotov, V.V. Computer modeling of the behavior of flue-element casings of water-moderated water-cooled power reactors under accident conditions with azimuthal temperature inhomogeneities. At Energy 63, 501–505 (1987). https://doi.org/10.1007/BF01125145

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  • DOI: https://doi.org/10.1007/BF01125145

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