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Comparison of the results of calculations and post-reactor investigations of VVÉR-1000 fuel elements with burnup 49 MW·days/kg

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Abstract

The results of calculations performed with the PINw99, TRANSURANUS (V1M1V03), and TOPRA-2 computer programs are compared with data obtained from post-reactor investigations of fuel elements which operated for four years in the No. 1 unit of the Zaparozh’e nuclear power plant with a VVÉR-1000 reactor to burnup ≈ 49 MW·days/kg. The initial data are analyzed, and a comparison is made of the computed and experimental elongation of the fuel elements (49 fuel elements), the yield of gaseous fission products and the subcladding pressure (35 fuel elements), and the decrease of cladding diameter and fuel-cladding gap width. It is shown that these computer programs can be used to calculate VVÉR fuel elements.

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Authors and Affiliations

  1. Institute for Nuclear Research and Nuclear Power, Bulgarian Academy of Sciences, Bulgaria

    G. Passage & S. Stefanova

  2. Russian Science Center Kurchatov Institute, Russia

    A. S. Shcheglov & V. N. Proselkov

Authors
  1. G. Passage
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  2. S. Stefanova
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  3. A. S. Shcheglov
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  4. V. N. Proselkov
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Translated from Atomnaya Énergiya, Vol. 101, No. 6, pp. 413–420, December, 2006.

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Passage, G., Stefanova, S., Shcheglov, A.S. et al. Comparison of the results of calculations and post-reactor investigations of VVÉR-1000 fuel elements with burnup 49 MW·days/kg. At Energy 101, 869–875 (2006). https://doi.org/10.1007/s10512-006-0183-4

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  • DOI: https://doi.org/10.1007/s10512-006-0183-4

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