The design of the ITER electron cyclotron launchers recently reached the preliminary design level - the last major milestone 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 (EL) for plasma heating and four upper launchers (UL) for plasma mode stabilization (neoclassical tearing modes and the sawtooth instability). A wide steering angle range of the ULs allows focusing of the beam 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, including the optical system and the structural components. Highlights of the design include the torus CVD-diamond windows, the frictionless, front steering mechanism and the plasma facing blanket shield module (BSM). Numerical simulations as well as prototype tests are used to verify the design

Preliminary design of the ITER ECH Upper Launcher

Cirant S;Farina D;Moro A;Platania P;Ramponi G;Sozzi C;
2013

Abstract

The design of the ITER electron cyclotron launchers recently reached the preliminary design level - the last major milestone 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 (EL) for plasma heating and four upper launchers (UL) for plasma mode stabilization (neoclassical tearing modes and the sawtooth instability). A wide steering angle range of the ULs allows focusing of the beam 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, including the optical system and the structural components. Highlights of the design include the torus CVD-diamond windows, the frictionless, front steering mechanism and the plasma facing blanket shield module (BSM). Numerical simulations as well as prototype tests are used to verify the design
2013
Istituto di fisica del plasma - IFP - Sede Milano
Inglese
88
11
2761
2766
6
http://www.sciencedirect.com/science/article/pii/S0920379613003347
Sì, ma tipo non specificato
ITER
Electron cyclotron heating
Mm-wave optics
Diamond windows
Prototyping
Testing
29
info:eu-repo/semantics/article
262
Strauss, D; Aiello, G; Chavan, R; Cirant, S; Debaar, M; Farina, D; Gantenbein, G; Goodman, Tp; Henderson, Ma; Kasparek, W; Kleefeldt, K; Landis, Jd; M...espandi
01 Contributo su Rivista::01.01 Articolo in rivista
restricted
   EU Fusion for ITER Applications
   EUFORIA
   FP7
   211804
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/259506
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