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The Influence of Long-Term Annealing Simulating Parameters of Dry Storage of VVER-1000 Fuel Rods on Mechanical Properties of Claddings from E110 Alloy in the Longitudinal Direction

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Inorganic Materials: Applied Research Aims and scope

Abstract

This article presents the experimental results of mechanical properties of fuel rod claddings from E110 zirconium alloy in the longitudinal direction that operated in fuel assemblies of VVER-1000 nuclear reactors to the fuel burnup of ~20 and ~70 MW d/kg U before and after post-radiation annealing at 380°C for 468 days. The changes in strength and plastic properties of the cladding in longitudinal direction were analyzed in comparison with its properties before and after irradiation and with their changes in the transverse direction. The changes in mechanical properties of the cladding are explained as a function of radiation damage of its structure.

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Funding

This work was supported by the Russian Foundation for Basic Research, project no. 19-08-00799 A.

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Authors and Affiliations

  1. State Scientific Center—Research Institute of Atomic Reactors (RIAR), 433510, Dimitrovgrad, Russia

    G. P. Kobylyansky, A. O. Mazaev, E. A. Zvir, S. G. Eremin, E. V. Chertopyatov & A. V. Obukhov

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  1. G. P. Kobylyansky
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  2. A. O. Mazaev
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  3. E. A. Zvir
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  4. S. G. Eremin
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  5. E. V. Chertopyatov
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  6. A. V. Obukhov
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Corresponding authors

Correspondence to G. P. Kobylyansky, E. A. Zvir or S. G. Eremin.

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Translated by I. Moshkin

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Kobylyansky, G.P., Mazaev, A.O., Zvir, E.A. et al. The Influence of Long-Term Annealing Simulating Parameters of Dry Storage of VVER-1000 Fuel Rods on Mechanical Properties of Claddings from E110 Alloy in the Longitudinal Direction. Inorg. Mater. Appl. Res. 13, 842–847 (2022). https://doi.org/10.1134/S2075113322030170

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