A remotely steered millimetre wave launcher for electron cyclotron heating and current drive on ITER

被引:6
|
作者
Bongers, W. A. [1 ]
Graswinckel, M. F. [1 ]
Goede, A. P. H. [1 ]
Kasparek, W. [5 ]
Danilov, I. [2 ]
Fernandez Curto, A. [3 ]
de Baar, M. R. [1 ]
van den Berg, M. A. [1 ]
Donne, A. J. H. [1 ]
Elzendoorn, B. S. Q. [1 ]
Heidinger, R. [2 ]
Ivanov, P. [4 ]
Kruijt, O. G. [1 ]
Lamers, B. [1 ]
Meier, A. [2 ]
Piosczyk, B. [2 ]
Plaum, B. [5 ]
Ronden, D. M. S. [1 ]
Thoen, D. J. [1 ]
Schmid, M. [2 ]
Verhoeven, A. G. A. [1 ]
机构
[1] FOM, EURATOM Assoc, Inst Plasma Phys Rijnhuizen, NL-3430 BE Nieuwegein, Netherlands
[2] Assoc FZK EURATOM, Forschungszentrum, D-76021 Karlsruhe, Germany
[3] CIEMAT, EURATOM Assoc, Lab Nacl Fus, E-28040 Madrid, Spain
[4] ELVA 1 Mm Wave Div, Riga, Latvia
[5] Univ Stuttgart, Inst Plasmaforsch, D-70569 Stuttgart, Germany
关键词
Remote steering launcher; Electron cyclotron heating and current drive; ITER; TEARING MODE STABILIZATION; ANTENNA; ECRH; LOSSES; DESIGN; SYSTEM; TESTS;
D O I
10.1016/j.fusengdes.2009.07.001
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
High-power millimetre wave beams employed on ITER for heating and Current drive at the 170 GHz electron cyclotron resonance frequency require agile steering and tight focusing of the beams to suppress neoclassical tearing modes. This paper presents experimental validation of the remote steering (RS) concept of the ITER upper port millimetre wave beam launcher. Remote steering at the entrance of the upper port launcher rather than at the plasma side offers advantages in reliability and maintenance of the mechanically Vulnerable steering system. A one-to-one scale mock-up consisting of a transmission line, mitre bends, remote steering unit, vacuum window, square corrugated waveguide and front mirror simulates the ITER launcher design configuration. Validation is based on low-power heterodyne measurements of the complex amplitude and phase distribution of the steered Gaussian beam. High-power (400 kW) short Pulse (10 ms) operation under vacuum, diagnosed by calorimetry and thermography of the near- and far-field beam patterns, confirms high-power operation, but shows increased power loss attributed to deteriorating input beam quality compared with low-power operation. Polarization measurements show little variation with steering, which is important for effective current drive requiring elliptical polarization for O-mode excitation. Results show that a RS range Of LIP to -12 to +12 can be achieved with acceptable beam quality. These measurements confirm the back-up design of the ITER ECRH&CD launcher with future application for DEMO. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:69 / 86
页数:18
相关论文
共 50 条
  • [21] Advanced launcher design options for electron cyclotron current drive on ITER based on remote steering
    Graswinckel, M. R.
    Bongers, W. A.
    de Baar, M. R.
    van den Berg, M. A.
    Denisov, G.
    Donne, A. J. H.
    Elzendoorn, B. S. Q.
    Goede, A. P. H.
    Heidinger, R.
    Kuzikov, S.
    Kruijt, O. G.
    Kruizinga, B.
    Moro, A.
    Poli, E.
    Ronden, D. M. S.
    Saibene, G.
    Thoen, D. J.
    Verhoeven, A. G. A.
    NUCLEAR FUSION, 2008, 48 (05)
  • [22] High power experiments of remote steering launcher for electron cyclotron heating and current drive
    Takahashi, K
    Moeller, CP
    Sakamoto, K
    Hayashi, K
    Imai, T
    FUSION ENGINEERING AND DESIGN, 2003, 65 (04) : 589 - 598
  • [23] Electron cyclotron heating and current drive
    Westerhof, E
    FUSION TECHNOLOGY, 1998, 33 (2T): : 235 - 240
  • [24] Electron cyclotron heating and current drive
    Westerhof, E
    FUSION TECHNOLOGY, 1996, 29 (2T): : 252 - 257
  • [25] Electron cyclotron heating and current drive
    FOM-Instituut voor Plasmafysica, 'Rijnhuizen', Nieuwegein, Netherlands
    Fusion Technol, 2 T (235-240):
  • [26] Power requirements for electron cyclotron current drive and ion cyclotron resonance heating for sawtooth control in ITER
    Chapman, I. T.
    Graves, J. P.
    Sauter, O.
    Zucca, C.
    Asunta, O.
    Buttery, R. J.
    Coda, S.
    Goodman, T.
    Igochine, V.
    Johnson, T.
    Jucker, M.
    La Haye, R. J.
    Lennholm, M.
    NUCLEAR FUSION, 2013, 53 (06)
  • [27] THE ENGINEERING ANALYSIS IN SUPPORT OF THE ITER ELECTRON CYCLOTRON HEATING AND CURRENT DRIVE TRANSMISSION LINES
    Ronden, D. M. S.
    Henderson, M. A.
    Becket, B.
    Bigelow, T.
    Caughman, J.
    Darbos, C.
    Gandini, F.
    Nazare, C.
    Rasmussen, D.
    Udintsev, V.
    FUSION SCIENCE AND TECHNOLOGY, 2011, 59 (04) : 718 - 728
  • [28] Status of the ITER Ion Cyclotron Heating and Current Drive System
    Lamalle, P.
    Beaumont, B.
    Kazarian, F.
    Gassmann, T.
    Agarici, G.
    Montemayor, T. Alonzo
    Bamber, R.
    Bernard, J. -M.
    Boilson, D.
    Cadinot, A.
    Calarco, F.
    Colas, L.
    Courtois, X.
    Deibele, C.
    Durodie, F.
    Fano, J.
    Fredd, E.
    Goulding, R.
    Greenough, N.
    Hillairet, J.
    Jacquinot, J.
    Kaye, A. S.
    Kocan, M.
    Labidi, H.
    Leichtle, D.
    Loarte, A.
    McCarthy, M.
    Messiaen, A.
    Meunier, L.
    Mukherjee, A.
    Oberlin-Harris, C.
    Patel, A. M.
    Peters, B.
    Rajnish, K.
    Rasmussen, D.
    Sanabria, R.
    Sartori, R.
    Singh, R.
    Swain, D.
    Trivedi, R. G.
    Turner, A.
    RADIOFREQUENCY POWER IN PLASMAS, 2015, 1689
  • [29] Potential of electron cyclotron current drive in ITER regimes
    Ramponi, G
    Lazzaro, E
    Nowak, S
    RADIO FREQUENCY POWER IN PLASMAS, 1997, (403): : 203 - 206
  • [30] Heating and current drive by electron cyclotron waves
    Prater, R
    PHYSICS OF PLASMAS, 2004, 11 (05) : 2349 - 2376