Design of the ITER upper port electron cyclotron heating and current drive system based on remote steering

TitleDesign of the ITER upper port electron cyclotron heating and current drive system based on remote steering
Publication TypeJournal Article
Year of Publication2008
AuthorsMF Graswinckel, M.A van den Berg, W.A Bongers, A.JH Donne, A.PH Goede, N.L Cardozo, D.MS Ronden, A.GA Verhoeven
JournalFusion Science and Technology
Volume53
Number1
Pagination208-219
Date PublishedJan
Type of ArticleArticle
ISBN Number1536-1055
Accession NumberISI:000252680200020
KeywordsBEAM-TRACING CODE, ECCD, electron cyclotron heating and current drive, ITER, remote steering, TEARING MODE STABILIZATION, TOKAMAK
Abstract

A design is presented for the electron cyclotron (EC) heating and current drive system of the ITER upper port launchers based on the remote steering (RS) concept. In this concept the millimeter-wave beam is steered by a mirror that is located at the back end of the launcher waveguide. The RS concept has the advantage that the mirror steering mechanism can be situated in the secondary vacuum of the ITER machine where neutron flux and beryllium and tritium contamination is reduced. This allows simpler maintenance relative to a system with a plasma-facing steering mechanism. The optimization is carried out on the quasi-optical elements of the system, including the mirror shapes and positions. The design is assessed for its effectiveness in stabilizing the neoclassical tearing mode (NTM) over a wide range of ITER reference scenarios. The stabilization performance is quantified in terms of the parameter eta(ntm), expressing the ratio between the peak EC wave-driven current density and the bootstrap current density, which parameter should exceed 1.2. The performance is also evaluated in terms of beam-focusing properties and power loading on the mirrors, and an empirical relation between beam size and eta(ntm) has been established. The performance achieved meets the requirements for NTM stabilization in all but one of the ITER reference scenarios.

URL<Go to ISI>://000252680200020
Division

Fusion Physics

PID

a7989414fe473939ca918c4338ba8127

Alternate TitleFusion Sci. Technol.

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