(EX3/3) Mode Coupling Trigger of Tearing Modes in ECW Heated Discharges in
FTU
S. Cirant1), E. Lazzaro1),
A. Bruschi1), P. Buratti2), R. Coelho3),
M. De Benedetti2), G. Granucci1),
A. Jacchia1), S. Nowak1), G. Pucella2),
G. Ramponi1), P. Smeulders2),
A. Smolyakov4), C. Sozzi1),
O. Tudisco2), B. Angelini2),
M. L. Apicella2), G. Apruzzese2),
E. Barbato2), L. Bertalot2),
A. Bertocchi2), G. Bracco2),
G. Buceti2), A. Cardinali2),
C. Centioli2), R. Cesario2),
S. Ciattaglia2), V. Cocilovo2),
F. Crisanti2), R. De Angelis2),
B. Esposito2), D. Frigione2),
L. Gabellieri2), F. Gandini1),
G. Gatti2), E. Giovannozzi2),
C. Gormezano2), M. Grolli2),
H. Kroegler2), M. Leigheb2),
G. Maddaluno2), M. Marinucci2),
G. Mazzitelli2), P. Micozzi2),
F. P. Orsitto2), D. Pacella2),
L. Panaccione2), M. Panella2),
V. Pericoli-Ridolfini2), L. Pieroni2),
S. Podda2), G. B. Righetti2),
F. Romanelli2), S. E. Segre2),
A. Simonetto1), E. Sternini2),
N. Tartoni2), A. A. Tuccillo2),
V. Vitale2), G. Vlad2), V. Zanza2),
M. Zerbini2), F. Zonca2)
1) Associazione EURATOM-ENEA-CNR, Istituto di Fisica del Plasma, CNR, Milano, Italy
2) Associazione EURATOM-ENEA sulla Fusione, C.R. Frascati, Frascati, Roma, Italy
3) Associação EURATOM/IST, Centro de Fusão Nuclear, 1096 Lisbon, Portugal
4) University of Saskatchewan, Saskatoon, Canada
5) INFM and Università di Roma ``Tor Vergata'', Roma Italy
Abstract. In recent ECRH experiments on FTU tokamak the destabilization of
(2,1) tearing modes, coupled to the (1,1) mode, has been observed. The
dynamics of the rotating island can be described by a Rutherford-type
equation, where mode coupling, inertial effects and resistive walls effects
are included. TM dynamics is influenced by the position of the absorbing
layer with respect to the island, to the extent that the mode can be
completely suppressed if absorption occurs at the island radial position,
with a precision in the order of the island size. EC absorption leading to
TM stabilization is localized on the island by mechanical steering of the EC
beam, and not by adjusting the toroidal field or forcing the plasma column
in the right position for stabilization. Stabilization is achieved at a
minimum ECRH power of
0.15POH. TM stabilization improves
significantly the energy confinement in the plasma core.
IAEA 2001