DocumentCode
2434260
Title
Plasma disruptions in ITER and the ECH upper port plug design
Author
Strauss, D. ; Heidinger, R. ; Hailfinger, G. ; Kleefeldt, K. ; Meier, A. ; Scherer, T. ; Spaeh, P. ; Vaccaro, A.
Author_Institution
Inst. fur Materialforschung I, Forschungszentrum Karlsruhe GmbH, Karlsruhe
fYear
2008
fDate
15-19 June 2008
Firstpage
1
Lastpage
1
Abstract
During ITER operation malfunctions of the control system due to excessively large perturbations and for special configurations can lead to vertical displacement events (VDE), where a vertical plasma movement is followed by a fast or slow plasma current quench. As a result during the plasma breakdown induced eddy and halo currents cause severe loads on the in-vessel components. For the upper port plug (UPP) structures in ITER the upward VDEs with the subsequent fast current quench are the most critical disruptions. The upper port design requires a plug length of about 5 m with a spacing of 10 mm at the first wall to the neighboring panels. One of the major challenges in the port plug design is to remain within the 10 mm gap during the disruption. The presented ECH UPP structural design cycle combines numerical analysis with manufacturing and prototype issues such as complex double wall structures and joining qualities.
Keywords
Tokamak devices; plasma toroidal confinement; ECH UPP structural design cycle; ECH upper port plug design; ITER operation malfunctions; plasma disruptions; vertical displacement events; Control systems; Displacement control; Electric breakdown; Manufacturing; Numerical analysis; Plasma materials processing; Plugs; Prototypes;
fLanguage
English
Publisher
ieee
Conference_Titel
Plasma Science, 2008. ICOPS 2008. IEEE 35th International Conference on
Conference_Location
Karlsruhe
ISSN
0730-9244
Print_ISBN
978-1-4244-1929-6
Electronic_ISBN
0730-9244
Type
conf
DOI
10.1109/PLASMA.2008.4590614
Filename
4590614
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