Damage to plasma-facing components (PFCS) from plasma instabilities remains a major obstacle to a successful tokamak concept. The extent of the damage depends on the detailed physics of the disrupting plasma, as well as on the physics of plasma-material interactions. A comprehensive computer package called High Energy Interaction with General Heterogeneous Target Systems (HEIGHTS) has been developed and consists of several integrated computer models that follow the beginning of a plasma disruption at the scrape-off layer (SOL) through the transport of the eroded debris and splashed target materials to nearby locations as a result of the deposited energy. The package can study, for the first time, plasma-turbulent behavior in the SOL and pre...
The provision of a particle and power exhaust solution which is compatible with first-wall component...
Intense deposition of energy in short times on fusion reactor components during a plasma disruption ...
Metallic materials such as tungsten and beryllium are candidates for the design of the plasma facing...
A comprehensive computer package, High Energy Interaction with General Heterogeneous Target Systems ...
Damage to plasma-facing and nearby components due to plasma instabilities remains a major obstacle t...
Surface and structural damage to plasma-facing components (PFCs) due to the frequent loss of plasma ...
Abstract-Safe and reliable operation is still one of the major challenges in the development of fusi...
The design of a suitable interface between plasma heated at millions of kelvin and the environment i...
Surface and structural damage to plasma-facing components due to the frequent loss of plasma confine...
Loss of plasma confinement causes surface and structural damage to plasma-facing materials (PFMs) an...
Damage to plasma-facing components (PFCs) and structural materials during abnormal plasma behavior s...
Plasma/material interactions (PMI) during four types of plasma transient/instabilities is a critical...
For modelling of plasma shield efficiency and erosion by vaporization of the ITER slot divertor the ...
The provision of a particle and power exhaust solution which is compatible with first-wall component...
Understanding the key processes occurring in the tokamak scrape-off layer (SOL) is becoming of the o...
The provision of a particle and power exhaust solution which is compatible with first-wall component...
Intense deposition of energy in short times on fusion reactor components during a plasma disruption ...
Metallic materials such as tungsten and beryllium are candidates for the design of the plasma facing...
A comprehensive computer package, High Energy Interaction with General Heterogeneous Target Systems ...
Damage to plasma-facing and nearby components due to plasma instabilities remains a major obstacle t...
Surface and structural damage to plasma-facing components (PFCs) due to the frequent loss of plasma ...
Abstract-Safe and reliable operation is still one of the major challenges in the development of fusi...
The design of a suitable interface between plasma heated at millions of kelvin and the environment i...
Surface and structural damage to plasma-facing components due to the frequent loss of plasma confine...
Loss of plasma confinement causes surface and structural damage to plasma-facing materials (PFMs) an...
Damage to plasma-facing components (PFCs) and structural materials during abnormal plasma behavior s...
Plasma/material interactions (PMI) during four types of plasma transient/instabilities is a critical...
For modelling of plasma shield efficiency and erosion by vaporization of the ITER slot divertor the ...
The provision of a particle and power exhaust solution which is compatible with first-wall component...
Understanding the key processes occurring in the tokamak scrape-off layer (SOL) is becoming of the o...
The provision of a particle and power exhaust solution which is compatible with first-wall component...
Intense deposition of energy in short times on fusion reactor components during a plasma disruption ...
Metallic materials such as tungsten and beryllium are candidates for the design of the plasma facing...