Tungsten has been chosen as the divertor armour material in ITER and is the main candidate material for plasma-facing components for future fusion reactors. Interaction of plasma components with the material leads to degradation of the performance and thus the lifetime of the in-vessel components. On top of that special attention is drawn to tritium retention in the reactors vessel from a safety point of view, since tritium is radioactive material. In order to gain better understanding of the mechanisms driving accumulation of plasma components in the material and subsequent degradation of the material, atomistic simulations are employed. The focus of this work is on so-called self trapping of H and He atoms or, in other words, Frenkel pair...
AbstractWe carry out generalized-ensemble molecular dynamics simulations of the formation of small h...
Tungsten is the prime candidate material for divertor applications in future nuclear reactors (e.g. ...
Tungsten has been chosen as the plasma-facing wall material in fusion reactors, due to its high dens...
Tungsten has been chosen as the divertor armour material in ITER and is the main candidate material ...
Tungsten has been chosen as the divertor armour material in ITER and is the main candidate material ...
The role of self-trapping and defect trapping of hydrogen and helium implanted into tungsten has bee...
Tungsten as a plasma facing material is the predominant contender for future Tokamak reactor environ...
The field of plasma confinement and path toward achieving thermonuclear fusion started with experime...
Molecular Dynamics Simulations of hydrogen diffusion and retention behavior near subsurface defects ...
In this work we developed an embedded atom method potential for large scale atomistic simulations in...
In this work we developed an embedded atom method potential for large scale atomistic simulations in...
It is important to develop an understanding of the evolution of W microstructure the conditions the ...
Magnetic confinement fusion is a promising technology for electricity production due to available fu...
The interaction of H and He interstitial atoms with 1/2 and loops in tungsten (W) was studied by m...
The interaction of H and He interstitial atoms with 1/2 and loops in tungsten (W) was studied by m...
AbstractWe carry out generalized-ensemble molecular dynamics simulations of the formation of small h...
Tungsten is the prime candidate material for divertor applications in future nuclear reactors (e.g. ...
Tungsten has been chosen as the plasma-facing wall material in fusion reactors, due to its high dens...
Tungsten has been chosen as the divertor armour material in ITER and is the main candidate material ...
Tungsten has been chosen as the divertor armour material in ITER and is the main candidate material ...
The role of self-trapping and defect trapping of hydrogen and helium implanted into tungsten has bee...
Tungsten as a plasma facing material is the predominant contender for future Tokamak reactor environ...
The field of plasma confinement and path toward achieving thermonuclear fusion started with experime...
Molecular Dynamics Simulations of hydrogen diffusion and retention behavior near subsurface defects ...
In this work we developed an embedded atom method potential for large scale atomistic simulations in...
In this work we developed an embedded atom method potential for large scale atomistic simulations in...
It is important to develop an understanding of the evolution of W microstructure the conditions the ...
Magnetic confinement fusion is a promising technology for electricity production due to available fu...
The interaction of H and He interstitial atoms with 1/2 and loops in tungsten (W) was studied by m...
The interaction of H and He interstitial atoms with 1/2 and loops in tungsten (W) was studied by m...
AbstractWe carry out generalized-ensemble molecular dynamics simulations of the formation of small h...
Tungsten is the prime candidate material for divertor applications in future nuclear reactors (e.g. ...
Tungsten has been chosen as the plasma-facing wall material in fusion reactors, due to its high dens...