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Impact of plastic deformation on plasma induced damage and deuterium retention in tungsten

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Abstract

Recent theoretical and subsequent experimental studies suggest that the uptake and release of deuterium (D) in tungsten (W) under high flux ITER-relevant plasma exposure is controlled by dislocation microstructure. Thanks to numerical calculations, a comprehensive mechanism for the nucleation and growth of D bubbles on dislocation network was proposed. The process of bubble nucleation can be described as D atom trapping at a dislocation line, its in-core migration, the coalescence of several D atoms into a multiple cluster eventually transforming into a nano-bubble. This view implies that the initial microstructure might be crucial for D uptake and degradation of the sub-surface layer under prolonged plasma exposure. In this work, we apply several experimental techniques to investigate the microstructure and mechanical properties of surface and sub-surface layer of W in recrystallized and plastically-deformed condition exposed to the high flux plasma. We use transmission and scanning electron microscopy, thermal desorption spectroscopy as well as nano-indentation measurements.

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Authors and Affiliations

  1. Structural Materials Group, Institute of Nuclear Materials Science, SCK·CEN, Mol, 2400, Belgium

    A. Bakaeva, D. Terentyev & A. Dubinko

  2. Department of Applied Physics, Ghent University, St. Pietersnieuwstraat 41, 9000, Ghent, Belgium

    A. Bakaeva & A. Dubinko

Authors
  1. A. Bakaeva
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  2. D. Terentyev
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  3. A. Dubinko
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Bakaeva, A., Terentyev, D. & Dubinko, A. Impact of plastic deformation on plasma induced damage and deuterium retention in tungsten. MRS Advances 2, 3347–3352 (2017). https://doi.org/10.1557/adv.2017.428

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  • DOI: https://doi.org/10.1557/adv.2017.428

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