Despite being a subject of long-term research on fusion-reactor structural materials, the behaviour of hydrogen in tungsten under plasma exposure remains unclear. Here, the explicit transmission electron microscopy observations for recrystallised W after hydrogen plasma exposure are successfully obtained. These are the first observations to show the intra-granular blisters are located on the {100} planes. Molecular dynamics simulations confirm the hydrogen blister initiating at <100> dislocation core behaved similarly to those in experiment. We propose that the widely reported intra-granular hydrogen blisters are nucleated at the <100> edge dislocation core and develop along the (100) plane in tungsten.</p
Knowledge of a material’s thermal stability under extreme synergistic particle and heat loads is cru...
The blistering behaviour of tungsten surfaces exposed to very high fluxes (1–2 × 1024/m2/s) of low e...
Tungsten is a leading candidate material for the diverter in future nuclear fusion reactors. Previou...
Despite being a subject of long-term research on fusion-reactor structural materials, the behaviour ...
Due to a lack of direct experimental results, the detailed mechanisms that govern the blistering beh...
By irradiating a tungsten sample for transmission electron microscopy with deuterium plasma at 230 K...
\u3cp\u3eIn this work, the microstructure evolution in the near-surface of tungsten under hydrogen (...
In this letter, a comprehensive mechanism for the nucleation and growth of bubbles on dislocations u...
AbstractUp to now, analyzing the production of dislocation-type defects in the subsurface region of ...
Up to now, analyzing the production of dislocation-type defects in the subsurface region of plasma o...
Blistering of tungsten (W) surfaces due to deuterium (D) implantation was investigated by a sequence...
This study presents experimental results on hydrogen blister formation on powder metallurgy tungsten...
Taking the example of tungsten, we demonstrate that high-flux plasma exposure of recrystallized and ...
The high-flux deuterium plasma impinging on a divertor degrades the long-termthermo-mechanical perfo...
Intense hydrogen plasma interactions with tungsten occur in the divertor region of ITER and the effe...
Knowledge of a material’s thermal stability under extreme synergistic particle and heat loads is cru...
The blistering behaviour of tungsten surfaces exposed to very high fluxes (1–2 × 1024/m2/s) of low e...
Tungsten is a leading candidate material for the diverter in future nuclear fusion reactors. Previou...
Despite being a subject of long-term research on fusion-reactor structural materials, the behaviour ...
Due to a lack of direct experimental results, the detailed mechanisms that govern the blistering beh...
By irradiating a tungsten sample for transmission electron microscopy with deuterium plasma at 230 K...
\u3cp\u3eIn this work, the microstructure evolution in the near-surface of tungsten under hydrogen (...
In this letter, a comprehensive mechanism for the nucleation and growth of bubbles on dislocations u...
AbstractUp to now, analyzing the production of dislocation-type defects in the subsurface region of ...
Up to now, analyzing the production of dislocation-type defects in the subsurface region of plasma o...
Blistering of tungsten (W) surfaces due to deuterium (D) implantation was investigated by a sequence...
This study presents experimental results on hydrogen blister formation on powder metallurgy tungsten...
Taking the example of tungsten, we demonstrate that high-flux plasma exposure of recrystallized and ...
The high-flux deuterium plasma impinging on a divertor degrades the long-termthermo-mechanical perfo...
Intense hydrogen plasma interactions with tungsten occur in the divertor region of ITER and the effe...
Knowledge of a material’s thermal stability under extreme synergistic particle and heat loads is cru...
The blistering behaviour of tungsten surfaces exposed to very high fluxes (1–2 × 1024/m2/s) of low e...
Tungsten is a leading candidate material for the diverter in future nuclear fusion reactors. Previou...