DocumentCode :
1949476
Title :
A proposed scraper element to protect the end of the W7-X divertor target elements
Author :
Peacock, A. ; Kisslinger, J. ; Boscary, J. ; Geiger, J. ; Hurd, F. ; König, R. ; Krychowiak, M. ; Stadler, R. ; Smirnow, M. ; Tretter, J. ; Werner, A.
Author_Institution :
Eur. Comm., EURATOM Assoc., Garching, Germany
fYear :
2011
fDate :
26-30 June 2011
Firstpage :
1
Lastpage :
5
Abstract :
The three main areas of the W7-X divertor target are: the horizontal target, the vertical target and the high iota tail, with a pumping gap between the horizontal and vertical targets. For each of the standard operational scenarios the target has been designed so that, based on vacuum field calculations, the plasma strike points lie away from the ends of the target. Each target consists of CFC armoured water cooled poloidally running target elements capable of operating reliably in these central regions at up to 10MW/m2 in steady state operation, as necessary for the standard configurations. Due to the U-turn shape of the cooling channel at the pumping gap end of the elements the cooling is not optimal and a reduced performance is expected. However, recent studies of experiment scenarios, also now taking into account the influence of bootstrap currents, showed that the strike point drifts over the ends of the target elements adjacent to the pumping gap on the L/R time scale; potentially leading to damage of the elements in these scenarios. Various operational methods have been studied to satisfactorily avoid this situation without success. The paper describes design changes being made to improve the ability of the end of the elements to accept reasonable power levels, however it is not expected that the elements in these regions will meet the full power requirements. Hence, this paper also describes the design of a protection element; the purpose of this so-called “scraper element” is to intercept the power to the targets before the full power reaches the sensitive end of the elements. This is done without reducing significantly the pumping at the pumping gap and addresses issues such as how to control local impurity flows. The programme of work concerning design and technology qualification still needed to realise this scraper element is described.
Keywords :
fusion reactor design; fusion reactor divertors; fusion reactor targets; plasma impurities; plasma toroidal confinement; plasma transport processes; stellarators; CFC armoured water cooled poloidally running target elements; W7-X divertor target element; bootstrap current; high iota tail; horizontal target; local impurity flow control; plasma strike point; pumping gap; scraper element analysis; steady state operation; vacuum field calculations; vertical target; Cooling; Heating; Divertor; W7-X; plasma target;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
Conference_Location :
Chicago, IL
ISSN :
1078-8891
Print_ISBN :
978-1-4577-0669-1
Electronic_ISBN :
1078-8891
Type :
conf
DOI :
10.1109/SOFE.2011.6052300
Filename :
6052300
Link To Document :
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