Design of a new ECRH launcher for FTU tokamak

被引:29
作者
Bin, W. [1 ]
Bruschi, A. [1 ]
Cirant, S. [1 ]
Granucci, G. [1 ]
Mantovani, S. [2 ]
Moro, A. [1 ]
Nowak, S. [1 ]
机构
[1] EURATOM ENEA CNR Assoc, Ist Fis Plasma Piero Caldirola, I-20125 Milan, Italy
[2] CR Frascati, Assoc EURATOM ENEA Fus, I-00044 Rome, Italy
关键词
ECRH launcher; MHD instability; O-X-B mode conversion; Millimeter waves; MODE CONVERSION; ANTENNA; PLASMA;
D O I
10.1016/j.fusengdes.2008.11.071
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
The present ECRH launcher installed on a single equatorial port of FTU tokamak was designed to inject four beams independently steered continuously in poloidal direction and in a set of predetermined toroidal angies. The launching mirrors can be moved only shot by shot. New experimental programmes for control of MHD instabilities with ECH/ECCD and heating of over-dense plasmas with ECBW require new launcher respectively with fast-steerable mirrors and increased toroidal capabilities. The required scanning speed for tracking the rational surfaces in the FTU plasma is 1 cm in 10 ms in poloidal direction, while the maximum toroidal angle needed for O-X-B heating scheme is around +/- 40 degrees. Two ECRH lines, feeding the old launcher, will be switched to the new launcher, located in a different equatorial position, capable of launching two independent beams from small movable mirrors in the plasma proximity. A control on the power deposition width will be achieved by changing the beam radius in the plasma using an optical system composed by two mirrors (zooming range 17-28 mm). Place has been reserved for future arrangements of additional components, e.g. a remote steering waveguide. A dedicated feedback control for the poloidal motion of the launching mirrors is being developed, in order to adapt the tracking of the power deposition location to the dynamic changes of magnetic surfaces in real-time. The maximum toroidal angle impacts strongly on the movable mirror design; dimensions (height around 90 mm, width around 54 mm) are limited by the port width (=80 mm) and the need to preserve the maximum steering angle. Since the mirrors will not be actively cooled, temperature control will be achieved by covering the backside with a high emissivity coating, to obtain an efficient radiative cooling. A detailed description of the launcher is presented in the paper. (C) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码:451 / 456
页数:6
相关论文
共 18 条
[1]   WAVES IN A PLASMA IN A MAGNETIC FIELD [J].
BERNSTEIN, IB .
PHYSICAL REVIEW, 1958, 109 (01) :10-21
[2]   Advances in high power calorimetric matched loads for short pulses and CW gyrotrons [J].
Bin, W. ;
Bruschi, A. ;
Cirant, S. ;
Erckmann, V. ;
Gandini, F. ;
Granucci, G. ;
Hollmann, F. ;
Laqua, H. P. ;
Mellera, V. ;
Muzzini, V. ;
Nardone, A. ;
Noke, F. ;
Piosczyk, B. ;
Purps, F. ;
Rzesnicki, T. ;
Schmid, M. ;
Sozzi, C. ;
Spies, W. ;
Spinicchia, N. ;
Stoner, M. .
FUSION ENGINEERING AND DESIGN, 2007, 82 (5-14) :775-784
[3]   High-power millimeter-wave calorimetric beam absorbers [J].
Bruschi, A. ;
Bin, W. ;
Cirant, S. ;
Gandini, F. ;
Mellera, V. ;
Muzzini, V. .
FUSION SCIENCE AND TECHNOLOGY, 2008, 53 (01) :62-68
[4]   A NEW LAUNCHER FOR REAL-TIME ECRH EXPERIMENTS ON FTU [J].
Bruschi, A. ;
Bin, W. ;
Cirant, S. ;
Granucci, G. ;
Mantovani, S. ;
Moro, A. ;
Nowak, S. .
FUSION SCIENCE AND TECHNOLOGY, 2009, 55 (01) :94-107
[5]   ECRH antenna at 140 GHz on FTU Tokamak [J].
Bruschi, A ;
Bozzi, R ;
Cirant, S ;
Gandini, F ;
Granucci, G ;
Mantovani, S ;
Mellera, V ;
Muzzini, V ;
Nardone, A ;
Nowak, S ;
Simonetto, A ;
Sozzi, C ;
Spinicchia, N .
FUSION ENGINEERING AND DESIGN, 2001, 53 (53) :431-441
[6]   ECH/ECCD applications for MHD studies and automatic control in FTU tokamak [J].
Cirant, S. ;
Berrino, J. ;
Buratti, P. ;
D'Antona, G. ;
Gandini, F. ;
Granucci, G. ;
Iannone, E. ;
Lazzaro, E. ;
Mellera, V. ;
Muzzini, V. ;
Smeulders, P. ;
Tudisco, O. .
FUSION SCIENCE AND TECHNOLOGY, 2008, 53 (01) :174-183
[7]   Overview of electron cyclotron heating and electron cyclotron current drive launcher development in magnetic fusion devices [J].
Cirant, Sante .
FUSION SCIENCE AND TECHNOLOGY, 2008, 53 (01) :12-38
[8]   Tests of a 105 Ghz prototype diplexer-combiner based on square corrugated waveguide [J].
D'Arcangelo, O. ;
Bin, W. ;
Bruschi, A. ;
Kasparek, W. ;
Moro, A. ;
Muzzini, V. ;
Plaum, B. ;
Simonetto, A. .
FUSION ENGINEERING AND DESIGN, 2009, 84 (2-6) :656-659
[9]   Effects of two-dimensional inhomogeneity in O-X mode conversion in tokamak plasmas [J].
Gospodchikov, E. D. ;
Shalashov, A. G. ;
Suvorov, E. V. .
FUSION SCIENCE AND TECHNOLOGY, 2008, 53 (01) :261-278
[10]   Overview of the ITER EC upper launcher [J].
Henderson, M. A. ;
Heidinger, R. ;
Strauss, D. ;
Bertizzolo, R. ;
Bruschi, A. ;
Chavan, R. ;
Ciattaglia, E. ;
Cirant, S. ;
Collazos, A. ;
Danilov, I. ;
Dolizy, F. ;
Duron, J. ;
Farina, D. ;
Fischer, U. ;
Gantenbein, G. ;
Hailfinger, G. ;
Kasparek, W. ;
Kleefeldt, K. ;
Landis, J. -D. ;
Meier, A. ;
Moro, A. ;
Platania, P. ;
Plaum, B. ;
Poli, E. ;
Ramponi, G. ;
Saibene, G. ;
Sanchez, F. ;
Sauter, O. ;
Serikov, A. ;
Shidara, H. ;
Sozzi, C. ;
Spaeh, P. ;
Udintsev, V. S. ;
Zohm, H. ;
Zucca, C. .
NUCLEAR FUSION, 2008, 48 (05)