DocumentCode
2882134
Title
Preliminary design of the ITER ECH upper launcher
Author
Strauss, D. ; Aiello, G. ; Chavan, R. ; Cirant, S. ; deBaar, M. ; Farina, D. ; Gantenbein, G. ; Goodman, T. ; Henderson, M.A. ; Kasparek, W. ; Kleefeldt, K. ; Landis, J.-D. ; Meier, A. ; Moro, A. ; Plaum, B. ; Poli, E. ; Ramponi, G. ; Ronden, D. ; Saibene
Author_Institution
Assoc. KIT-EURATOM, Karlsruhe Inst. of Technol., Karlsruhe, Germany
fYear
2011
fDate
26-30 June 2011
Firstpage
1
Lastpage
1
Abstract
The design of the ITER electron cyclotron launchers recently reached the preliminary design level -the last major step before design finalization. The ITER ECH system contains 24 installed gyrotrons providing a maximum ECH injected power of 20 MW through transmission lines towards the tokamak. There are two EC launcher types both using a front steering mirror; one Equatorial Launcher for plasma heating and four Upper Launchers (UL) for plasma mode stabilization (neoclassical tearing modes and the sawtooth instability). A wide steering angle of the ULs allows to focus on magnetic islands which are expected on the rational magnetic flux surfaces q = 1 (sawtooth instability), q = 3/2 and q = 2 (NTMs). In this paper the preliminary design of the ITER ECH UL is presented, which includes the optical system and the port plug structural components. Highlights of the design include the torus CVD-diamond windows, the frictionless, front steering mechanism and the plasma facing blanket shield module. Numerical simulations as well as prototype tests are used to verify the design.
Keywords
Tokamak devices; cyclotrons; gyrotrons; numerical analysis; plasma heating; plasma simulation; plasma toroidal confinement; sawtooth instability; tearing instability; ITER ECH upper launcher design; electron cyclotron launchers; equatorial launcher; front steering mirror; gyrotrons; magnetic islands; neoclassical tearing modes; numerical simulations; optical system; plasma facing blanket shield module; plasma heating; plasma mode stabilization; port plug structural components; power 20 MW; rational magnetic flux surfaces; sawtooth instability; tokamak; torus CVD diamond windows; transmission lines;
fLanguage
English
Publisher
ieee
Conference_Titel
Plasma Science (ICOPS), 2011 Abstracts IEEE International Conference on
Conference_Location
Chicago, IL
ISSN
0730-9244
Print_ISBN
978-1-61284-330-8
Electronic_ISBN
0730-9244
Type
conf
DOI
10.1109/PLASMA.2011.5993099
Filename
5993099
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