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Determination of the effective hydraulic diameter of a defect in VVER-440 RK-3 fuel-element cladding

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Atomic Energy Aims and scope

A procedure for calculating the normalized kinetic dependence of radionuclide efflux from unsealed fuel elements in the third-generation working cassettes (RK-3) of VVER-440 and the computational results are presented. The work is done by modeling the behavior of an unsealed fuel element in a working and stopped reactor using the RTOP-SA and RTOP-KGO computational codes. The effective hydraulic diameter of a defect can be evaluated using the computational results and experimental data obtained by monitoring the seal tightness of fuel-element cladding with pressure cycling at the power plant.

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References

  1. V. G. Zborovskii, V. V. Likhanskii, I. A. Evdokimov, et al., “Modeling of radionuclide efflux during testing for seal tightness of fuel elements in a stopped reactor,” Mat. Modelir., 23, No. 7, 145–160 (2011).

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Authors and Affiliations

  1. Gidropress Experimental Design Bureau (OKB Gidropress), Podolsk, Moscow Oblast, Russia

    N. A. Ivanov

  2. State Science Center of the Russian Federation – Troitsk Institute for Innovation and Fusion Research (GNTs RF TRINITI), Troitsk, Russia

    V. V. Likhanskii, A. A. Sorokin & V. G. Zborovskii

Authors
  1. N. A. Ivanov
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  2. V. V. Likhanskii
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  3. A. A. Sorokin
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  4. V. G. Zborovskii
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Additional information

Translated from Atomnaya Énergiya, Vol. 113, No. 4, pp. 214–218, October, 2012.

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Ivanov, N.A., Likhanskii, V.V., Sorokin, A.A. et al. Determination of the effective hydraulic diameter of a defect in VVER-440 RK-3 fuel-element cladding. At Energy 113, 265–270 (2013). https://doi.org/10.1007/s10512-013-9628-8

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  • DOI: https://doi.org/10.1007/s10512-013-9628-8

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