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Featured researches published by G. Ehrke.


ieee symposium on fusion engineering | 2013

Wendelstein 7-X high heat flux components

A. Peacock; J. Boscary; M. Czerwinski; G. Ehrke; H. Greuner; P. Junghanns; B. Mendelevitch; M. Smirnow; R. Stadler; H. Tittes; J. Tretter

The actively water-cooled In-Vessel Components (IVCs) of the stellarator Wendelstein 7-X consist of the divertor, the first wall protection components, the port liners, each designed for different loading conditions, and the associated pipework, the control coils, the cryo-pump system, the Glow discharge electrodes, and a set of diagnostics. The divertor, designed for high heat fluxes, is a set of 10 target and baffle units arranged along the plasma surface. The design and production of these high heat flux (HHF) components is a challenging task. The divertor target elements, which are based on flat CFC (carbon-carbon fibre composite) tiles bonded via active metal casting onto CuCrZr cooling structures required intensive development and testing to reach a reliable performance; removing, under stationary conditions, 10 MW/m2. Industrially manufactured high quality target elements have been delivered and assessed, and the process of incorporating them into assembly units, so-called modules, has begun. The time scale for the completion of the HHF divertor has been held for the last four years and the final delivery of the HHF divertor is still planned in 2017. In parallel to the realization of the divertor the remaining IVCs have been defined, developed, designed and fabricated and the installation of many of these components has begun. Some of these components can also be expected, for a short period of time, to receive high heat loads approaching those of the divertor. These components will be described, in detail, from conception to realization.


IEEE Transactions on Plasma Science | 2014

Status of High Heat Flux Components at W7-X

A. Peacock; J. Boscary; M. Czerwinski; G. Ehrke; H. Greuner; P. Junghanns; B. Mendelevitch; M. Smirnow; R. Stadler; H. Tittes; J. Tretter

The actively water-cooled in-vessel components (IVCs) of the stellarator Wendelstein 7-X consist of the divertor, the first wall protection components, the port liners, each designed for different loading conditions, and the associated pipework, the control coils, the cryo-pump system, the Glow discharge electrodes, and a set of diagnostics. The divertor, designed for high heat fluxes (HHFs), is a set of 10 target and baffle units arranged along the plasma surface. The design and production of these HHF components is a challenging task. The divertor target elements, which are based on flat carbon-carbon fiber composite tiles bonded via active metal casting onto CuCrZr cooling structures required intensive development and testing to reach a reliable performance; removing, under stationary conditions, 10 MW/m2. Industrially manufactured high quality target elements have been delivered and assessed, and the process of incorporating them into assembly units, so-called modules, has begun. The time scale for the completion of the HHF divertor has been held for the last four years and the final delivery of the HHF divertor is still planned in 2017. In parallel to the realization of the divertor, most of the remaining IVCs have been defined, developed, designed, and fabricated and the installation of many of these components has begun. Some of these components can also be expected, for a short period of time, to receive high heat loads approaching those of the divertor. These components will be described, in detail, from conception to realization.


IEEE Transactions on Plasma Science | 2018

Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper

J. Boscary; H. Greuner; G. Ehrke; B. Böswirth; Z. Wang; E. Clark; A. Lumsdaine; J. Tretter; P. Junghanns; R. Stadler; D. McGinnis; J. Lore

Heat load calculations have indicated the possible overloading of the ends of the water-cooled divertor facing the pumping gap beyond their technological limit. The intention of the scraper is the interception of some of the plasma fluxes both upstream and downstream before they reach the divertor surface. The scraper is divided into six modules of four plasma facing components (PFCs); each module has four PFCs hydraulically connected in series by two water boxes (inlet and outlet). A full-scale prototype of one module has been manufactured. Development activities have been carried out to connect the water boxes to the cooling pipes of the PFCs by tungsten inert gas internal orbital welding. This prototype was successfully tested in the GLADIS facility with 17 MW/m2 for 500 cycles. The results of these activities have confirmed the possible technological basis for a fabrication of the water-cooled scraper.


ieee/npss symposium on fusion engineering | 2011

The superconducting magnet system of the stellarator Wendelstein 7-X

Thomas Rummel; K. Risse; G. Ehrke; K. Rummel; Andre John; Thomas Mönnich; Klaus-Peter Buscher; Walter H. Fietz; R. Heller; O. Neubauer; A. Panin


Fusion Engineering and Design | 2016

Prototyping phase of the high heat flux scraper element of Wendelstein 7-X

J. Boscary; H. Greuner; G. Ehrke; B. Böswirth; Zhongwei Wang; E. Clark; A. Lumsdaine; J. Tretter; D. McGinnis; J. Lore; Kivanc Ekici


Fusion Engineering and Design | 2018

Upgrades of edge, divertor and scrape-off layer diagnostics of W7-X for OP1.2

D. Hathiramani; A. Ali; G. Anda; T. Barbui; C. Biedermann; A. Charl; D. Chauvin; G. Czymek; C. P. Dhard; P. Drewelow; A. Dudek; F. Effenberg; G. Ehrke; M. Endler; D. A. Ennis; J. Fellinger; O. Ford; S. Freundt; D. Gradic; K. Grosser; J. H. Harris; H. Hölbe; M. Jakubowski; M. Knaup; G. Kocsis; R. König; M. Krause; T. Kremeyer; P. Kornejew; M. Krychowiak


symposium on fusion technology | 2018

Erosion and deposition investigations on Wendelstein 7-X first wall components for the first operation phase in divertor configuration

C. P. Dhard; M. Mayer; S. Brezinsek; S. Masuzaki; G. Motojima; R. König; T. S. Pedersen; R. Neu; D. Hathiramani; M. Krause; G. Ehrke; R. Cristian; T. Schwarz-Selinger; M. Balden; J. W. Coenen; Christian Linsmeier; D. Naujoks; O. Neubauer; M. Rack; M. Tokitani; J. Oelmann; C. Li; M. Rasinski; D. Höschen; M. Yajima


IEEE Transactions on Plasma Science | 2018

Thermal and Mechanical Analysis of the Wendelstein7-X Cryo-Vacuum Pump Plug-In

Z. Wang; G. Ehrke; B. Mendelevitch; J. Boscary; R. Stadler


symposium on fusion technology | 2017

Structural analysis of the W7-X cryopump during the superconducting coil fast discharge event

Z. Wang; G. Ehrke; B. Mendelevitch; J. Boscary; R. Stadler


ieee symposium on fusion engineering | 2017

Design and test of W7-X water-cooled Divertor Scraper

J. Boscary; H. Greuner; G. Ehrke; B. Böswirth; Z. Wang; E. Clark; A. Lumsdaine; J. Tretter; P. Junghanns; R. Stadler; D. McGinnis; J. Lore

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A. Lumsdaine

Oak Ridge National Laboratory

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D. McGinnis

Oak Ridge National Laboratory

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