Overview of the ITER EC H&CD system and its capabilities

TitleOverview of the ITER EC H&CD system and its capabilities
Publication TypeJournal Article
Year of Publication2011
AuthorsT. Omori, M.A Henderson, F. Albajar, S. Alberti, U. Baruah, T.S Bigelow, B. Becket, R. Bertizzolo, T. Bonicelli, A. Brusch, J.B Caughman, R. Chavan, S. Cirant, A. Collazos, D. Cox, C. Darbos, MR de Baar, G. Denisov, D. Farina, F. Gandini, T. Gassmann, T.P Goodman, R. Heidinger, J.P Hogge, S. Illy, O. Jean, J. Jin, K. Kajiwara, W. Kasparek, A. Kasugai, S. Kern, N. Kobayashi, H. Kumric, J.D Landis, A. Moro, C. Nazare, Y. Oda, I. Pagonakis, B. Piosczyk, P. Platania, B. Plaum, E. Poli, L. Porte, D. Purohit, G. Ramponi, S.L Rao, D.A Rasmussen, D.MS Ronden, T. Rzesnicki, G. Saibene, K. Sakamoto, F. Sanchez, T. Scherer, M.A Shapiro, C. Sozzi, P. Spaeh, D. Strauss, O. Sauter, K. Takahashi, R.J Temkin, M. Thumm, M.Q Tran, V.S. Udintsev, H. Zohm
JournalFusion Engineering and Design
Volume86
Issue6-8
Number6-8
Pagination951-954
Date PublishedOct
Type of ArticleArticle; Proceedings Paper
ISBN Number0920-3796
KeywordsDESIGN, Electron Cyclotron, gyrotron, ITER, launcher, MHD stabilization
Abstract

The Electron Cyclotron (EC) system for the ITER tokamak is designed to inject >= 20 MW RF power into the plasma for Heating and Current Drive (H&CD) applications. The EC system consists of up to 26 gyrotrons (between 1 and 2 MW each), the associated power supplies, 24 transmission lines and 5 launchers. The EC system has a diverse range of applications including central heating and current drive, current profile tailoring and control of plasma magneto-hydrodynamic (MUD) instabilities such as the sawtooth and neoclassical tearing modes (NTMs). This diverse range of applications requires the launchers to be capable of depositing the EC power across nearly the entire plasma cross section. This is achieved by two types of antennas: an equatorial port launcher (capable of injecting up to 20 MW from the plasma axis to mid-radius) and four upper port launchers providing access from inside of mid radius to near the plasma edge. The equatorial launcher design is optimized for central heating, current drive and profile tailoring, while the upper launcher should provide a very focused and peaked current density profile to control the plasma instabilities. The overall EC system has been modified during the past 3 years taking into account the issues identified in the ITER design review from 2007 and 2008 as well as integrating new technologies. This paper will review the principal objectives of the EC system, modifications made during the past 2 years and how the design is compliant with the principal objectives. (C) 2011 ITER Organization. Published by Elsevier B.V. All rights reserved.

DOI10.1016/j.fusengdes.2011.02.040
Division

FP

Department

TP

PID

c370f03eff7f1a27a15a35be0d59bc06

Alternate TitleFusion Eng. Des.

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