High performance advanced tokamak regimes in DIII-D for next-step experiments

被引:18
作者
Greenfield, CM
Murakami, M
Ferron, JR
Wade, MR
Luce, TC
Petty, CC
Menard, JE
Petrie, TW
Allen, SL
Burrell, KH
Casper, TA
DeBoo, JC
Doyle, EJ
Garofalo, AM
Gorelov, IA
Groebner, RJ
Hobirk, J
Hyatt, AW
Jayakumar, RJ
Kessel, CE
La Haye, RJ
Jackson, GL
Lohr, J
Makowski, MA
Pinsker, RI
Politzer, PA
Prater, R
Strait, EJ
Taylor, TS
West, WP
机构
[1] Gen Atom Co, San Diego, CA 92186 USA
[2] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[3] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[4] Lawrence Livermore Natl Lab, Livermore, CA USA
[5] Univ Calif Los Angeles, Los Angeles, CA USA
[6] Columbia Univ, New York, NY USA
[7] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
关键词
D O I
10.1063/1.1692133
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Advanced Tokamak (AT) research in DIII-D [K. H. Burrell for the DIII-D Team, in Proceedings of the 19th Fusion Energy Conference, Lyon, France, 2002 (International Atomic Energy Agency, Vienna, 2002) published on CD-ROM] seeks to provide a scientific basis for steady-state high performance operation in future devices. These regimes require high toroidal beta to maximize fusion output and poloidal beta to maximize the self-driven bootstrap current. Achieving these conditions requires integrated, simultaneous control of the current and pressure profiles, and active magnetohydrodynamic stability control. The building blocks for AT operation are in hand. Resistive wall mode stabilization via plasma rotation and active feedback with nonaxisymmetric coils allows routine operation above the no-wall beta limit. Neoclassical tearing modes are stabilized by active feedback control of localized electron cyclotron current drive (ECCD). Plasma shaping and profile control provide further improvements. Under these conditions, bootstrap supplies most of the current. Steady-state operation requires replacing the remaining Ohmic current, mostly located near the half radius, with noninductive external sources. In DIII-D this current is provided by ECCD, and nearly stationary AT discharges have been sustained with little remaining Ohmic current. Fast wave current drive is being developed to control the central magnetic shear. Density control, with divertor cryopumps, of AT discharges with edge localized moding H-mode edges facilitates high current drive efficiency at reactor relevant collisionalities. A sophisticated plasma control system allows integrated control of these elements. Close coupling between modeling and experiment is key to understanding the separate elements, their complex nonlinear interactions, and their integration into self-consistent high performance scenarios. Progress on this development, and its implications for next-step devices, will be illustrated by results of recent experiment and simulation efforts. (C) 2004 American Institute of Physics.
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收藏
页码:2616 / 2626
页数:11
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