Overview of electron cyclotron heating and electron cyclotron current drive launcher development in magnetic fusion devices

被引:6
作者
Cirant, Sante [1 ]
机构
[1] CNR, Ist Fis Plasma, Assoc Euratom CNR Sulla Fus, I-20125 Milan, Italy
关键词
ITER EC launcher; ECH and EC current drive; millimeter waves;
D O I
10.13182/FST08-A1650
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
In any system designed for electron cyclotron (EC) heating (ECH) and EC current drive in fusion plasmas, the launcher is the matching element between the plasma and the transmission line. Only an appropriate launcher achieves efficient use of the gyrotron power for the many different high-power EC H&CD applications. The frontier is now set at approximate to 4 MW of launched power at 110 to 140 GHz for approximate to 10 s, to be further moved to approximate to 10 MW, 1000 s in the near future. ITER will push the limit to 20 MW, 170 GHz. The workhorse of the antenna system is the front steering setup consisting of a movable mirror, or a mirror array, in front of the hot plasma, which provides for full flexibility in the EC H&CD applications. However, because of the concern associated with cooled and movable parts in a hostile environment, air arrangement with movable mirrors positioned far from the vessel port, and connected to the plasma by imaging waveguides, is being developed as a remote steering backup solution. In a reactor, where flexibility is much less relevant than reliability, the situation could reverse. Techniques for a radial scan of the deposition layer different from front beam steering are discussed in this paper. The ideal goal would be a 100% coupling of the launched EC power, to occur within approximate to 2% of the plasma size and through pipes of size negligible with respect to the vessel, without negative impact on plasma periphery in spite of the high power densities transmitted through the edge.
引用
收藏
页码:12 / 38
页数:27
相关论文
共 172 条
[71]   Measurements of ohmic losses of metallic reflectors at 140 GHz using a 3-mirror resonator technique [J].
Kasparek, W ;
Fernandez, A ;
Hollmann, F ;
Wacker, R .
INTERNATIONAL JOURNAL OF INFRARED AND MILLIMETER WAVES, 2001, 22 (11) :1695-1707
[72]   Mirror development for the 140 GHz ECRH transmission system on the stellarator W7-X [J].
Kasparek, W ;
Empacher, L ;
Erckmann, V ;
Gantenbein, G ;
Hollmann, F ;
Laqua, HP ;
Schüller, PG ;
Weissgerber, M ;
Zohm, H .
FUSION ENGINEERING AND DESIGN, 2001, 53 :545-551
[73]   Internal transport barrier formation in experiments with reverse magnetic shear in T-10 tokamak [J].
Kirneva, NA ;
Esipchuk, YV ;
Borschegovskij, AA ;
Vchistyakov, V ;
Gorbunov, EP ;
Denisov, VP ;
Dremin, MM ;
Kakurin, AM ;
Khimchenko, LN ;
Kislov, DA ;
Krylov, SV ;
Krupin, VA ;
Myalton, TB ;
Novikov, AY ;
Orlovskij, II ;
Pavlov, YD ;
Petrov, DP ;
Ploskirev, GN ;
Roy, IN ;
Ryjakov, DV ;
Shelukhin, DA ;
Skovoroda, AA ;
Skosirev, YV ;
Slepneva, LI ;
Sushkov, AV ;
Trukhin, VM ;
Trukhina, EV .
PLASMA PHYSICS AND CONTROLLED FUSION, 2005, 47 (10) :1787-1803
[74]  
Kislov DA, 2001, NUCL FUSION, V41, P1473, DOI 10.1088/0029-5515/41/10/314
[75]   DEMO plant design beyond ITER [J].
Konishi, S ;
Nishio, S ;
Tobita, K .
FUSION ENGINEERING AND DESIGN, 2002, 63-64 :11-17
[76]  
KRITZ A., 1982, Proceedings of the 3rd International Symposium on Heating in Toroidal Plasmas, V2, P707
[77]   Extension and characteristics of an ECRH plasma in LHD [J].
Kubo, S ;
Shimozuma, T ;
Yoshimura, Y ;
Notake, T ;
Idei, H ;
Inagaki, S ;
Yokoyama, M ;
Ohkubo, K ;
Kumazawa, R ;
Nakamura, Y ;
Saito, K ;
Seki, T ;
Mutoh, T ;
Watari, T ;
Narihara, K ;
Yamada, I ;
Ida, K ;
Takeiri, Y ;
Funaba, H ;
Ohyabu, N ;
Kawahata, K ;
Kaneko, O ;
Yamada, H ;
Itoh, K ;
Ashikawa, N ;
Emoto, M ;
Goto, M ;
Hamada, Y ;
Ido, T ;
Ikeda, K ;
Isobe, M ;
Khlopenkov, K ;
Kobuchi, T ;
Masuzaki, S ;
Minami, T ;
Miyazawa, J ;
Morisaki, T ;
Morita, S ;
Murakami, S ;
Muto, S ;
Nagaoka, K ;
Nagayama, Y ;
Nakanishi, H ;
Narushima, Y ;
Nishimura, K ;
Nishiura, M ;
Noda, N ;
Ohdachi, S ;
Oka, Y ;
Osakabe, M .
PLASMA PHYSICS AND CONTROLLED FUSION, 2005, 47 :A81-A90
[78]   RECTANGULAR CORRUGATED WAVE-GUIDE AND PARALLEL CORRUGATED PLATES FOR AN ELLIPTIC GAUSSIAN-BEAM [J].
OHKUBO, K ;
KUBO, S ;
SATO, M ;
IDEI, H ;
TAKITA, Y ;
KURODA, T .
FUSION ENGINEERING AND DESIGN, 1995, 26 (1-4) :325-333
[79]   Cross-machine benchmarking for ITER of neoclassical tearing mode stabilization by electron cyclotron current drive [J].
La Haye, R. J. ;
Prater, R. ;
Buttery, R. J. ;
Hayashi, N. ;
Isayama, A. ;
Maraschek, M. E. ;
Urso, L. ;
Zohm, H. .
NUCLEAR FUSION, 2006, 46 (04) :451-461
[80]   Higher stable beta by use of pre-emptive electron cyclotron current drive on DIII-D [J].
La Haye, RJ ;
Humphreys, DA ;
Ferron, JR ;
Luce, TC ;
Perkins, FW ;
Petty, CC ;
Prater, R ;
Strait, EJ ;
Welander, AS .
NUCLEAR FUSION, 2005, 45 (11) :L37-L41