A new divertor configuration (DIV-IIb) has been implemented in ASDEX Upgrade. In order to accommodate a large variety of plasma shapes with bottom triangularities (δ<sub>bot</sub>) up to 0.48, the outer strikepoint region was modified and the roof baffle was lowered and diminished at its outer part in comparison with the previous divertor (DIV-II). The inner part of the divertor strikepoint module remains unchanged, but a smooth transition to the central column is provided at the divertor entrance to minimize local hydrogen recycling. An increase in power density is observed due to geometrical reasons at the outer target, whereas the divertor radiation for similar configurations and discharge conditions is unchanged. The pumping characteris...
The elements of transport into and across the scrape-off layer in the poloidal divertor tokamak ASDE...
Recent experiments in ASDEX Upgrade aimed at improving the physics base for ITER and DEMO to prepare...
In 1997 the new ‘LYRA ’ divertor went into operation at ASDEX Upgrade and the neutral beam heating p...
A new divertor configuration (DIV-IIb) has been implemented in ASDEX Upgrade. In order to accommodat...
A new divertor configuration (DIV IIb) has been implemented in ASDEX Upgrade. In order to accommodat...
An overview of edge and divertor physics research on ASDEX Upgrade of relevance for next-step fusion...
Divertor detachment is a prerequisite for large burning plasma fusion devices. The understanding of ...
Abstract. In this article a new experimental classification of divertor detachment in ASDEX Upgrade ...
Improvements to the DIII-D tokamak have led to significant new research results and enhanced perform...
The divertor tokamak ASDEX Upgrade was operated up to now with two significantly different divertor ...
The medium size divertor tokamak ASDEX Upgrade (major and minor radii 1.65 m and 0.5 m, respectively...
The medium size divertor tokamak ASDEX Upgrade (major and minor radii 1.65 m and 0.5 m, respectively...
The elements of transport into and across the scrape-off layer in the poloidal divertor tokamak ASDE...
Recent experiments in ASDEX Upgrade aimed at improving the physics base for ITER and DEMO to prepare...
In 1997 the new ‘LYRA ’ divertor went into operation at ASDEX Upgrade and the neutral beam heating p...
A new divertor configuration (DIV-IIb) has been implemented in ASDEX Upgrade. In order to accommodat...
A new divertor configuration (DIV IIb) has been implemented in ASDEX Upgrade. In order to accommodat...
An overview of edge and divertor physics research on ASDEX Upgrade of relevance for next-step fusion...
Divertor detachment is a prerequisite for large burning plasma fusion devices. The understanding of ...
Abstract. In this article a new experimental classification of divertor detachment in ASDEX Upgrade ...
Improvements to the DIII-D tokamak have led to significant new research results and enhanced perform...
The divertor tokamak ASDEX Upgrade was operated up to now with two significantly different divertor ...
The medium size divertor tokamak ASDEX Upgrade (major and minor radii 1.65 m and 0.5 m, respectively...
The medium size divertor tokamak ASDEX Upgrade (major and minor radii 1.65 m and 0.5 m, respectively...
The elements of transport into and across the scrape-off layer in the poloidal divertor tokamak ASDE...
Recent experiments in ASDEX Upgrade aimed at improving the physics base for ITER and DEMO to prepare...
In 1997 the new ‘LYRA ’ divertor went into operation at ASDEX Upgrade and the neutral beam heating p...