Conceptual design of the ECH upper launcher system for ITER

Heidinger, R.; Bertizzolo, R.; Bruschi, A.; Chavan, R.; Cirant, S.; Collazos, A.; Baar, M. de; Elzendoorn, B.S.Q.; Farina, D.; Fischer, U.; Gafert, J.; Gandini, F.; Gantenbein, G.; Goede, A. P. H.; Goodman, T.; Hailfinger, G.; Henderson, M.; Kasparek, W.; Kleefeldt, K.; Landis, J.‐D.; Meier, Andreas; Moro, A.; Platania, P.; Poli, E.; Ramponi, G.; Saibene, G.; Sánchez, F.; Sauter, O.; Scherer, T.; Serikov, A.; Satō, Hiroyuki; Sozzi, C.; Spaeh, P.; Strauß, D.; Udintsev, V. S.; Vaccaro, A.; Zohm, H.; Zucca, C.

doi:10.1016/j.fusengdes.2008.11.002

Cited by 18 publications

(17 citation statements)

References 12 publications

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“…They offer a wide angular steering range sufficient to cover the required range for NTMs and the sawtooth instability. Based on the conceptual upper launcher design [13] the analysis of different optical beam paths [14] led to a modification of the optical design from a mitre bend solution towards a quasi-optical system, increasing the steering range and thereby the upper launcher performance. With the new "Extended Physics Launcher" (EPL, [15]) the steering angles of USM and LSM have been decoupled, the goal is to cover a range between ρ T =0.3 to near the plasma edge at ρ T =0.95.…”

Section: B the Millimeter-wave Systemmentioning

confidence: 99%

Preliminary design of the ITER ECH upper launcher

Strauß

Aiello

Chavan

et al. 2011

2011 Abstracts IEEE International Conference on Plasma Science

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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 CVDdiamond 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

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Section: B the Millimeter-wave Systemmentioning

confidence: 99%

Preliminary design of the ITER ECH upper launcher

Strauß

Aiello

Chavan

et al. 2011

2011 Abstracts IEEE International Conference on Plasma Science

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“…It is assumed, that these will be free-running oscillators (although gyro-amplifiers and phase-locking schemes are under development, but at present do not provide sufficient power). The gyrotrons are connected via evacuated corrugated HE 11 waveguide to 3 upper launchers [19] (UL; 8 beams each, mainly for NTM stabilization) and one equatorial launcher (EL; 24 beams, mainly for central heating and current drive). A central unit with mechanical waveguide switches allows connecting the gyrotrons either to the ULs or the EL.…”

Section: Options For Applications and Integration In The Ecrh System mentioning

confidence: 99%

High-power microwave diplexers for advanced ECRH systems

Kasparek

Petelin

Erckmann

et al. 2009

Fusion Engineering and Design

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In Electron cyclotron resonance heating systems, high-power multiplexers can be employed as power combiners, adjustable power dividers, fast switches to toggle the power between two launchers, as well as frequency sensitive directional couplers to combine heating and diagnostic applications on one launcher. In the paper, various diplexer designs for quasi-optical and corrugated waveguide transmission systems are discussed. Numerical calculations, low-power tests and especially high-power experiments performed at the ECRH system of W7-X are shown, which demonstrate the capability of these devices. Near term plans for applications on ASDEX Upgrade and FTU are presented. Based on the present results, options for implementation of power combiners and fast switches in the ECRH system of ITER is discussed.

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“…The paper is motivated to show the nuclear analyses' importance in the multidiscipline R&D work of several EURATOM Associations [1] striving for success of the recent design of the launcher in fulfilling its aims in ITER. Currently, the R&D work on the ECH launcher is managed and supported by the Fusion for Energy Joint Undertaking (F4E), and formerly-by the European Fusion Development Agreement (EFDA).…”

Section: Introductionmentioning

confidence: 99%

“…The purpose of the upper ECH launcher is to control the Magneto-Hydro-Dynamic (MHD) instabilities in the ITER plasma. This purpose can be fulfilled by a very localized and peaked profile of the current driven by mm-waves with a frequency of 170 GHZ and a power of 20 MW, which are injected into the plasma through the launcher Quasi-Optical (QO) mm-wave system [1].…”

Section: Introductionmentioning

confidence: 99%