@article{7412,
  author = {T. Omori and M. A. Henderson and F. Albajar and S. Alberti and U. Baruah and T. S. Bigelow and B. Becket and R. Bertizzolo and T. Bonicelli and A. Brusch and J. B. Caughman and R. Chavan and S. Cirant and A. Collazos and D. Cox and C. Darbos and M.R. de Baar and G. Denisov and D. Farina and F. Gandini and T. Gassmann and T. P. Goodman and R. Heidinger and J. P. Hogge and S. Illy and O. Jean and J. Jin and K. Kajiwara and W. Kasparek and A. Kasugai and S. Kern and N. Kobayashi and H. Kumric and J. D. Landis and A. Moro and C. Nazare and Y. Oda and I. Pagonakis and B. Piosczyk and P. Platania and B. Plaum and E. Poli and L. Porte and D. Purohit and G. Ramponi and S. L. Rao and D. A. Rasmussen and D. M. S. Ronden and T. Rzesnicki and G. Saibene and K. Sakamoto and F. Sanchez and T. Scherer and M. A. Shapiro and C. Sozzi and P. Spaeh and D. Strauss and O. Sauter and K. Takahashi and R. J. Temkin and M. Thumm and M. Q. Tran and V.S. Udintsev and H. Zohm},
  title = {Overview of the ITER EC H&CD system and its capabilities},
  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.
},
  year = {2011},
  journal = {Fusion Engineering and Design},
  volume = {86},
  number = {6-8},
  pages = {951-954},
  month = {Oct},
  isbn = {0920-3796},
  doi = {10.1016/j.fusengdes.2011.02.040},
  note = {ISI Document Delivery No.: 853KZTimes Cited: 1Cited Reference Count: 2526th Symposium on Fusion Technology (SOFT)SEP 27-OCT 01, 2010Porto, PORTUGALInst Plasmas Fusao Nucl (IPFN), Commiss European Union, Inst Soldadura Qualidade (ISQ), Fundacao Ciencia Tecnologia (FCT), Univ Tecnica Lisboa (UTL), TAP, Andante},
  language = {English},
}