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Open AccessJournal ArticleDOI

Surface morphology and deuterium retention in tungsten exposed to high flux D plasma at high temperatures

TLDR
In this paper, surface modifications and deuterium retention induced in tungsten by high fluxes (1024 m−2 s−1) low energy (38 eV) D ions were studied as a function of surface temperature.
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This article is published in Journal of Nuclear Materials.The article was published on 2015-02-01 and is currently open access. It has received 61 citations till now. The article focuses on the topics: Blisters & Tungsten.

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Multiscale modelling of the interaction of hydrogen with interstitial defects and dislocations in BCC tungsten

TL;DR: In this article, the authors derived analytical formulae for the number of hydrogen atoms forming the Cottrell atmosphere of a mesoscopic dislocation loop or an edge dislocation.
Journal ArticleDOI

Mechanism for orientation dependence of blisters on W surface exposed to D plasma at low temperature

TL;DR: In this article, the orientation dependence of blister formation induced by D plasma exposure at low temperature (about 523 K) on rolled tungsten and chemical vapor deposition (CVD) W samples was studied by scanning electron microscopy and electron backscatter diffraction.
Journal ArticleDOI

Subsurface deuterium bubble formation in W due to low-energy high flux deuterium plasma exposure

TL;DR: In this paper, the deuterium (D) bubbles formed in W exposed to high flux D plasma were researched by scanning electron microscopy and transmission electron microscope, and a layer of nano-sized bubbles were homogenously distributed in W subsurface region.
References
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Journal ArticleDOI

Plasma{material interactions in current tokamaks and their implications for next step fusion reactors

TL;DR: In this article, the authors review the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next-step fusion reactors.
Journal ArticleDOI

A full tungsten divertor for ITER: Physics issues and design status

TL;DR: In this article, the authors consider the risks engendered by the baseline divertor strategy with regard to known W plasma-material interaction issues and briefly present the current status of a possible full-tungsten (W) divertor design.
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