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Urso, L.*; Fischer, R.*; Isayama, Akihiko; ASDEX Upgrade Team; JT-60 Team
Plasma Physics and Controlled Fusion, 52(5), p.055012_1 - 055012_16, 2010/05
Times Cited Count：4 Percentile：15.96(Physics, Fluids & Plasmas)no abstracts in English
Urso, L.*; Zohm, H.*; Isayama, Akihiko; Maraschek, M.*; Poli, E.*; ASDEX Upgrade Team; JT-60 Team
Nuclear Fusion, 50(2), p.025010_1 - 025010_12, 2010/01
Times Cited Count：28 Percentile：71.87(Physics, Fluids & Plasmas)no abstracts in English
Sips, A. C. C.*; Casper, T.*; Doyle, E. J.*; Giruzzi, G.*; Gribov, Y.*; Hobirk, J.*; Hogeweij, G. M. D.*; Horton, L. D.*; Hubbard, A. E.*; Hutchinson, I.*; et al.
Nuclear Fusion, 49(8), p.085015_1 - 085015_11, 2009/08
Times Cited Count：53 Percentile：87.31(Physics, Fluids & Plasmas)Key parts of the ITER scenarios are determined by the capability of the proposed poloidal field (PF) coil set. They include the plasma breakdown at low loop voltage, the current rise phase, the performance during the flat top (FT) phase and a ramp down of the plasma. The ITER discharge evolution has been verified in dedicated experiments. New data are obtained from C-Mod, ASDEX Upgrade, DIII-D, JT-60U and JET. Results show that breakdown for 
0.23-0.33 V m
is possible unassisted (ohmic) for large devices like JET and attainable in devices with a capability of using ECRH assist. For the current ramp up, good control of the plasma inductance is obtained using a full bore plasma shape with early X-point formation. This allows optimization of the flux usage from the PF set. Additional heating keeps 
(3) 0.85 during the ramp up to 
= 3. A rise phase with an H-mode transition is capable of achieving (3) 0.7 at the start of the FT. Operation of the H-mode reference scenario at 
3 and the hybrid scenario at = 4-4.5 during the FT phase is documented, providing data for the (3) evolution after the H-mode transition and the (3) evolution after a back-transition to L-mode. During the ITER ramp down it is important to remain diverted and to reduce the elongation. The inductance could be kept 
1.2 during the first half of the current decay, using a slow 
ramp down, but still consuming flux from the transformer. Alternatively, the discharges can be kept in H-mode during most of the ramp down, requiring significant amounts of additional heating.
Urso, L.*; Zohm, H.*; Fischer, R.*; Isayama, Akihiko; Kamada, Yutaka; ASDEX Upgrade Team; JT-60 Team
Europhysics Conference Abstracts (CD-ROM), 32D, 4 Pages, 2008/00
no abstracts in English
Maggi, C. F.*; Groebner, R. J.*; Oyama, Naoyuki; Sartori, R.*; Horton, L. D.*; Sips, A. C. C.*; Suttrop, W.*; ASDEX Upgrade Team; Leonard, A.*; Luce, T. C.*; et al.
Nuclear Fusion, 47(7), p.535 - 551, 2007/07
Times Cited Count：63 Percentile：88.45(Physics, Fluids & Plasmas)Pedestal and global plasma parameters are compared in ELMy H-modes and improved confinement discharges from ASDEX Upgrade (AUG), DIII-D, JET and JT-60U with varying net input power. The pedestal top pressure increases moderately with power, in broad agreement with the power dependence of the H98(y,2) scaling. For all machines and all scenarios a robust correlation between the total and the pedestal thermal stored energy is observed. In AUG the improved confinement is due to improved pedestal confinement in improved H-modes with early heating and to both improved pedestal and core confinement in improved H-modes with late heating. In DIII-D the increase in confinement is due to improved confinement in the plasma core. JT-60U reversed shear H-modes have strong internal transport barriers and thus improved core performance. In all four tokamaks improved edge stability is correlated with increasing total 
and H98(y,2) increases with pedestal .
Maggi, C. F.*; Groebner, R. J.*; Oyama, Naoyuki; Sartori, R.*; Horton, L. D.*; Sips, A. C. C.*; Suttrop, W.*; ASDEX Upgrade Team; Leonard, T.*; Luce, T. C.*; et al.
Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03
Pedestal and global plasma parameters are compared in ELMy H-mode discharges from ASDEX Upgrade (AUG), DIII-D, JET and JT-60U. The increase in pedestal pressure (p
) with power is continuous, reflecting the continuous transition from "standard H-mode" to "improved confinement scenario". In AUG improved H-modes p increases with power due to an increase of both pedestal top density and temperature. In DIII-D p increases primarily due to an increase of the pedestal temperature. In JT-60U high 
H-modes at 
= 6.5 and high 
the improved confinement is due to an increase of 
, while in reversed shear H-modes to an increase of 
. In JET hybrid discharges at 1.4 MA 
increases with power and due to an increase of . In all four tokamaks improved edge stability is correlated to increasing total 
and H98(y,2) increases with pedestal .
Stober, J.*; Lomas, P. J.*; Saibene, G.*; Andrew, Y.*; Belo, P.*; Conway, G. D.*; Herrmann, A.*; Horton, L. D.*; Kempenaars, M.*; Koslowski, H.-R.*; et al.
Nuclear Fusion, 45(11), p.1213 - 1223, 2005/11
Times Cited Count：40 Percentile：76.37(Physics, Fluids & Plasmas)no abstracts in English
Hobirk, J.*; Oikawa, Toshihiro; Fujita, Takaaki; Fukuda, Takeshi; G
nter, S.*; Gruber, O.*; Isayama, Akihiko; Kamada, Yutaka; Kikuchi, Mitsuru; Maraschek, M.*; et al.
Europhysics Conference Abstracts (CD-ROM), 27A, 4 Pages, 2003/00
no abstracts in English
