International Workshop on Plasma-Facing Materials and Components for Fusion Applications, PFMC-12 (12. 2009. Julich, Germany
Investigation of plasma-material interaction under high transient heat flux in the experimental fusi...
Carbon based materials (CBMs) are used in fusion devices as plasma facing materials for decades. The...
The subject of the development of the WENDELSTEIN 7-X divertor is the manufacturing of approximately...
Qualification of tungsten (W) and graphite (C) based brazed plasma facing components (PFCs) is an im...
In future fusion devices, like in the stellarator Wendelstein 7-X. the target plates of the divertor...
The development of the fabrication technology of macro-brush configuration of tungsten (W) and carbo...
In spite of the remarkable progress in the design of in-vessel components for the divertor of the fi...
Finely dispersed Ti-doped isotropic graphites with 4 at.% Ti have been manufactured using synthetic ...
CX-2O02U and IG-430U coated by VPS-W were developed as a lighrweight high-Z plasma-facing material. ...
To simulate the cyclic HHF operations of the divertor components, actively cooled, brazed joint mock...
This paper is focused on various aspects of the development and testing of water cooled divertor PFC...
und durch die Fakultät für Maschinenwesen am 13.10.2009 angenommen. Für meine Familie The divertor d...
This project was aimed at hot shaping of titanium carbide/graphite and vanadium carbide/graphite com...
High heat fluxes to in-vessel components of nuclear fusion devices during normal operation and abnor...
Finely dispersed Ti- and Zr-doped isotropic graphites have been manufactured using three different s...
Investigation of plasma-material interaction under high transient heat flux in the experimental fusi...
Carbon based materials (CBMs) are used in fusion devices as plasma facing materials for decades. The...
The subject of the development of the WENDELSTEIN 7-X divertor is the manufacturing of approximately...
Qualification of tungsten (W) and graphite (C) based brazed plasma facing components (PFCs) is an im...
In future fusion devices, like in the stellarator Wendelstein 7-X. the target plates of the divertor...
The development of the fabrication technology of macro-brush configuration of tungsten (W) and carbo...
In spite of the remarkable progress in the design of in-vessel components for the divertor of the fi...
Finely dispersed Ti-doped isotropic graphites with 4 at.% Ti have been manufactured using synthetic ...
CX-2O02U and IG-430U coated by VPS-W were developed as a lighrweight high-Z plasma-facing material. ...
To simulate the cyclic HHF operations of the divertor components, actively cooled, brazed joint mock...
This paper is focused on various aspects of the development and testing of water cooled divertor PFC...
und durch die Fakultät für Maschinenwesen am 13.10.2009 angenommen. Für meine Familie The divertor d...
This project was aimed at hot shaping of titanium carbide/graphite and vanadium carbide/graphite com...
High heat fluxes to in-vessel components of nuclear fusion devices during normal operation and abnor...
Finely dispersed Ti- and Zr-doped isotropic graphites have been manufactured using three different s...
Investigation of plasma-material interaction under high transient heat flux in the experimental fusi...
Carbon based materials (CBMs) are used in fusion devices as plasma facing materials for decades. The...
The subject of the development of the WENDELSTEIN 7-X divertor is the manufacturing of approximately...