The subject of the development of the WENDELSTEIN 7-X divertor is the manufacturing of approximately 900 plasma facing components (PFCs) that meet all requirements for reliable long pulse and long-term plasma operation. The actively cooled PFCs are made of CFC NB31 as plasma facing material bonded by Active Metal Casting ® (AMC) copper interlayer onto CuCrZr cooling structure. The pre-series activities integrated extensive high heat flux (HHF) testing to assess the industrial manufacturing. Tests were performed in the GLADIS facility under load conditions similar to those expected during operation of W7-X. The investigations focused on the improvement of fatigue resistance of the CFC/Cu bonding. The results of the last HHF test campaign dem...
International audienceFor the development of a divertor for DEMO, the European WPDIV project is unde...
CX-2O02U and IG-430U coated by VPS-W were developed as a lighrweight high-Z plasma-facing material. ...
The first wall and the divertor in present-day or next step thermonuclear fusion devices are exposed...
Abstract—The actively water-cooled In-Vessel Components (IVCs) of the stellarator Wendelstein 7-X co...
This paper is focused on various aspects of the development and testing of water cooled divertor PFC...
The development of plasma facing components for next step fusion devices in Europe is strongly focus...
In future fusion devices, like in the stellarator Wendelstein 7-X. the target plates of the divertor...
The divertor target plates are the most thermally loaded in-vessel components in a fusion reactor wh...
The operation of W7-X stellarator for pulse length up to 30 minutes with 10 MW input power requires ...
With the aim to assess the option to start the ITER operation with a full tungsten divertor, an R&D ...
International audienceFor the development of a divertor for DEMO, the European WPDIV project is unde...
For a future commercial fusion reactor the First Wall of the breeding blanket will require a joint b...
International audienceFor the development of a divertor for DEMO, the European WPDIV project is unde...
International audienceFor the development of a divertor for DEMO, the European WPDIV project is unde...
International audienceFor the development of a divertor for DEMO, the European WPDIV project is unde...
International audienceFor the development of a divertor for DEMO, the European WPDIV project is unde...
CX-2O02U and IG-430U coated by VPS-W were developed as a lighrweight high-Z plasma-facing material. ...
The first wall and the divertor in present-day or next step thermonuclear fusion devices are exposed...
Abstract—The actively water-cooled In-Vessel Components (IVCs) of the stellarator Wendelstein 7-X co...
This paper is focused on various aspects of the development and testing of water cooled divertor PFC...
The development of plasma facing components for next step fusion devices in Europe is strongly focus...
In future fusion devices, like in the stellarator Wendelstein 7-X. the target plates of the divertor...
The divertor target plates are the most thermally loaded in-vessel components in a fusion reactor wh...
The operation of W7-X stellarator for pulse length up to 30 minutes with 10 MW input power requires ...
With the aim to assess the option to start the ITER operation with a full tungsten divertor, an R&D ...
International audienceFor the development of a divertor for DEMO, the European WPDIV project is unde...
For a future commercial fusion reactor the First Wall of the breeding blanket will require a joint b...
International audienceFor the development of a divertor for DEMO, the European WPDIV project is unde...
International audienceFor the development of a divertor for DEMO, the European WPDIV project is unde...
International audienceFor the development of a divertor for DEMO, the European WPDIV project is unde...
International audienceFor the development of a divertor for DEMO, the European WPDIV project is unde...
CX-2O02U and IG-430U coated by VPS-W were developed as a lighrweight high-Z plasma-facing material. ...
The first wall and the divertor in present-day or next step thermonuclear fusion devices are exposed...