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Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiation embrittlement. Experimental results

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Strength of Materials Aims and scope

For the assessment of the effect of irradiation-induced swelling on mechanical properties of an irradiated austenitic steel, investigations have been performed on 08Kh18N10T steel – base metal and weld – exposed to damaging dozes close in magnitude, within two different temperature ranges: (a) 330–340°C, where there occurs almost no swelling, and (b) 400–450°C, where a significant level of swelling (3–13%) is observed. Based on the investigation results, the temperature dependence of short-term mechanical properties is plotted for the irradiated metal. A comparative study of magnetization of the metal irradiated at various temperatures has been carried out. Fractographic examination of the tested specimens has been performed.

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Authors and Affiliations

  1. Federal State Unitary Enterprise Central Research Institute of Structural Materials “Prometey”, St. Petersburg, Russia

    B. Z. Margolin, I. P. Kursevich, A. A. Sorokin, A. N. Lapin & V. I. Kokhonov

  2. Federal State Unitary Enterprise “State Scientific Center – Research Institute of Atomic Reactors”, Dimitrovgrad, Russia

    V. S. Neustroev

Authors
  1. B. Z. Margolin
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  2. I. P. Kursevich
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  3. A. A. Sorokin
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  4. A. N. Lapin
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  5. V. I. Kokhonov
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  6. V. S. Neustroev
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Additional information

Translated from Problemy Prochnosti, No. 6, pp. 5–16, November–December, 2009.

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Margolin, B.Z., Kursevich, I.P., Sorokin, A.A. et al. Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiation embrittlement. Experimental results. Strength Mater 41, 593–602 (2009). https://doi.org/10.1007/s11223-009-9175-7

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  • DOI: https://doi.org/10.1007/s11223-009-9175-7

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