Advanced tokamak research in DIII-D

被引:30
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
Lao, LL
Lohr, J
Makowski, MA
Pinsker, RI
Politzer, PA
Prater, R
Staebler, GM
Strait, EJ
Taylor, TS
West, WP
机构
[1] Gen Atom Co, San Diego, CA 92186 USA
[2] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[3] Lawrence Livermore Natl Lab, Livermore, CA USA
[4] Univ Calif Los Angeles, Los Angeles, CA USA
[5] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
[6] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
关键词
D O I
10.1088/0741-3335/46/12B/019
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 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 high 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 by plasma rotation and active feedback with non-axisymmetric 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 inductively driven current, mostly located near the half radius, with non-inductive external sources. In DIII-D this current is provided by ECCD, and nearly stationary AT discharges have been sustained with little remaining inductive current. Fast wave current drive is being developed to control the central magnetic shear. Density control, with divertor cryopumps, of AT discharges with ELMing H-mode edges facilitates high current drive efficiency at reactor relevant collisionalities. An advanced plasma control system allows integrated control of these elements. Close coupling between modelling and experiment is key to understanding the separate elements, their complex nonlinear interactions, and their integration into self-consistent high performance scenarios. This approach has resulted in fully non-inductively driven plasmas with beta(N) less than or equal to 3.5 and beta(T) less than or equal to 3.6% sustained for up to 1 s, which is approximately equal to one current relaxation time. Progress in this area, and its implications for next-step devices, will be illustrated by results of these and other recent experiment and simulation efforts.
引用
收藏
页码:B213 / B233
页数:21
相关论文
共 54 条
[21]   Advanced tokamak operation using the DIII-D plasma control system [J].
Humphreys, DA ;
Ferron, JR ;
Garofalo, AM ;
Hyatt, AW ;
Jernigan, TC ;
Johnson, RD ;
La Haye, RJ ;
Leuer, JA ;
Okabayashi, M ;
Penaflor, BG ;
Scoville, JT ;
Strait, EJ ;
Walker, ML ;
Whyte, DG .
FUSION ENGINEERING AND DESIGN, 2003, 66-68 :663-667
[22]   Complete stabilization of a tearing mode in steady state high-βp H-mode discharges by the first harmonic electron cyclotron heating/current drive on JT-60U [J].
Isayama, A ;
Kamada, Y ;
Ide, S ;
Hamamatsu, K ;
Oikawa, T ;
Suzuki, T ;
Neyatani, Y ;
Ozeki, T ;
Ikeda, Y ;
Kajiwara, K .
PLASMA PHYSICS AND CONTROLLED FUSION, 2000, 42 (12) :L37-L45
[23]   High-beta steady-state research and future directions on the Japan Atomic Energy Research Institute Tokamak-60 Upgrade and the Japan Atomic Energy Research Institute Fusion Torus-2 Modified [J].
Ishida, S .
PHYSICS OF PLASMAS, 2004, 11 (05) :2532-2542
[24]  
KESSEL CE, 2003, P 30 EUR C CONTR F A, V27
[25]   Burning plasma confinement projections and renormalization of the GLF23 drift-wave transport model [J].
Kinsey, JE ;
Staebler, GM ;
Waltz, RE .
FUSION SCIENCE AND TECHNOLOGY, 2003, 44 (04) :763-775
[26]   Control of neoclassical tearing modes in DIII-D [J].
La Haye, RJ ;
Günter, S ;
Humphreys, DA ;
Lohr, J ;
Luce, TC ;
Maraschek, ME ;
Petty, CC ;
Prater, R ;
Scoville, JT ;
Strait, EJ .
PHYSICS OF PLASMAS, 2002, 9 (05) :2051-2060
[27]  
LAHAYE RJ, 2004, P 31 EUR C CONTR FUS
[28]   EQUILIBRIUM-ANALYSIS OF CURRENT PROFILES IN TOKAMAKS [J].
LAO, LL ;
FERRON, JR ;
GROEBNER, RJ ;
HOWL, W ;
STJOHN, H ;
STRAIT, EJ ;
TAYLOR, TS .
NUCLEAR FUSION, 1990, 30 (06) :1035-1049
[29]   AN OPTIMIZATION OF BETA IN THE DIII-D TOKAMAK [J].
LAZARUS, EA ;
LAO, LL ;
OSBORNE, TH ;
TAYLOR, TS ;
TURNBULL, AD ;
CHU, MS ;
KELLMAN, AG ;
STRAIT, EJ ;
FERRON, JR ;
GROEBNER, RJ ;
HEIDBRINK, WW ;
CARLSTROM, T ;
HELTON, FJ ;
HSIEH, CL ;
LIPPMANN, S ;
SCHISSEL, D ;
SNIDER, R ;
WROBLEWSKI, D .
PHYSICS OF FLUIDS B-PLASMA PHYSICS, 1992, 4 (11) :3644-3662
[30]   Progress towards steady-state operation and real-time control of internal transport barriers in JET [J].
Litaudon, X ;
Bécoulet, A ;
Crisanti, F ;
Wolf, RC ;
Baranov, YF ;
Barbato, E ;
Bécoulet, M ;
Budny, R ;
Castaldo, C ;
Cesario, R ;
Challis, CD ;
Conway, GD ;
De Baar, MR ;
De Vries, P ;
Dux, R ;
Eriksson, LG ;
Esposito, B ;
Felton, R ;
Fourment, C ;
Frigione, D ;
Garbet, X ;
Giannella, R ;
Giroud, C ;
Gorini, G ;
Hawkes, NC ;
Hellsten, T ;
Hender, TC ;
Hennequin, P ;
Hogeweij, GMD ;
Huysmans, GTA ;
Imbeaux, F ;
Joffrin, E ;
Lomas, PJ ;
Lotte, P ;
Maget, P ;
Mailloux, J ;
Mantica, P ;
Mantsin, MJ ;
Mazon, D ;
Moreau, D ;
Parail, V ;
Pericoli, V ;
Rachlew, E ;
Riva, M ;
Rimini, F ;
Sarazin, Y ;
Stratton, BC ;
Tala, TJJ ;
Tresset, G ;
Tudisco, O .
NUCLEAR FUSION, 2003, 43 (07) :565-572