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

Published online by Cambridge University Press:  15 June 2017

A. Bakaeva
Affiliation:
Structural Materials Group, Institute of Nuclear Materials Science, SCK·CEN, Mol, 2400, Belgium Department of Applied Physics, Ghent University, St. Pietersnieuwstraat 41, 9000 Ghent, Belgium
D. Terentyev*
Affiliation:
Structural Materials Group, Institute of Nuclear Materials Science, SCK·CEN, Mol, 2400, Belgium
A. Dubinko
Affiliation:
Structural Materials Group, Institute of Nuclear Materials Science, SCK·CEN, Mol, 2400, Belgium Department of Applied Physics, Ghent University, St. Pietersnieuwstraat 41, 9000 Ghent, Belgium
*
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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.

Type
Articles
Copyright
Copyright © Materials Research Society 2017 

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