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Simulation of Fatigue Processes in the Structural Materials of Reactor Vessels Over a 102 – 1012 Cycle Durability Range*

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Strength of Materials Aims and scope

The aggregate model of the evolutionary equation for fatigue damage accumulation in the structural materials of reactor vessels suffering from low- and high-cycle fatigue is presented. The reliability of the model is substantiated by comparing numerical results and experimental data.

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Authors and Affiliations

  1. Afrikantov Experimental Design Bureau for Mechanical Engineering, Nizhni Novgorod, Russia

    M. A. Bol’shukhin, M. N. Ereev, A. V. Kozin & V. A. Panov

  2. Rosatom State Corporation, Moscow, Russia

    A. V. Kaplienko

Authors
  1. M. A. Bol’shukhin
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  2. M. N. Ereev
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  3. A. V. Kozin
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  4. V. A. Panov
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  5. A. V. Kaplienko
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Additional information

*Paper presented at the International Scientific Conference Fatigue and Thermofatigue of Materials and Structural Components (Kiev, 2013).

Translated from Problemy Prochnosti, No. 5, pp. 109 – 114, September – October, 2014.

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Bol’shukhin, M.A., Ereev, M.N., Kozin, A.V. et al. Simulation of Fatigue Processes in the Structural Materials of Reactor Vessels Over a 102 – 1012 Cycle Durability Range*. Strength Mater 46, 672–676 (2014). https://doi.org/10.1007/s11223-014-9600-4

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  • DOI: https://doi.org/10.1007/s11223-014-9600-4

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