Extended JT-60U plasma regimes for high integrated performance

被引:80
作者
Kamada, Y [1 ]
机构
[1] Japan Atom Energy Res Inst, Naka Fus Res Estab, Naka, Ibaraki 31101, Japan
关键词
D O I
10.1088/0029-5515/41/10/302
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
With the main aim of providing the physics basis for ITER and steady state tokamak reactors, JT-60U has been optimizing operational concepts and extending discharge regimes towards simultaneous sustainment of high confinement, high beta (N), high bootstrap fraction, full non-inductive current drive, and efficient heat and particle exhaust utilizing a variety of heating, current drive, torque input and particle control capabilities. In the two advanced operation regimes (reversed magnetic shear (RS mode) and weak magnetic shear (high beta (p) mode)), ELMy H mode discharges characterized by both internal and edge transport barriers and by high bootstrap current fraction f(BS) have been sustained near the steady state current profile solutions under full non-inductive current drive with appropriate driven current profiles (high beta (p): HHy2 approximate to 1.4 and beta (N) approximate to 2.5 with negative ion based neutral beams (N-NBs); RS: HHy2 approximate to 2.2 and beta (N) approximate to 2 with f(BS) approximate to 80%). Multiple pellet injection has extended the density region with high confinement. These operational modes have been extended to the reactor relevant regime with small values of collisionality and normalized gyroradius, and T-e similar to T-i. In the RS regime, Q(DT)(eq) = 0.5 has been sustained for 0.8 s. Stability has been improved in the high beta (p) mode regime by suppression of the neoclassical tearing mode with local ECCD and in the RS mode regime by wall stabilization. The internal transport barrier structure has been controlled by toroidal rotation profile modification, and transport studies have revealed a semiglobal dynamics of the internal transport barrier structure. Simultaneous pumping at the inner and the outer divertor leg has enhanced He exhaust by similar to 40%. Argon puff experiments have improved confinement at high density with detached divertor owing to high pedestal temperature T-i(ped). In H modes, the core confinement degraded with decreasing T-i(ped), suggesting stiff core profiles. An operational region of grassy ELMs with small divertor heat load has been established at high triangularity, high q(95) and high beta (p). A record value of the neutral beam current drive efficiency of 1.55 x 10(19) A m(-2) W-1 has been demonstrated using N-NB. Abrupt large amplitude events causing a drop in neutron emission have been discovered with frequency inside the TAE gap. Disruption studies have clarified that runaway current is terminated by MHD fluctuations when the surface q decreases to 2-3.
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收藏
页码:1311 / 1325
页数:15
相关论文
共 38 条
[1]   High performance experiments in JT-60U reversed shear discharges [J].
Fujita, T ;
Kamada, Y ;
Ishida, S ;
Neyatani, Y ;
Oikawa, T ;
Ide, S ;
Takeji, S ;
Koide, Y ;
Isayama, A ;
Fukuda, T ;
Hatae, T ;
Ishii, Y ;
Ozeki, T ;
Shirai, H .
NUCLEAR FUSION, 1999, 39 (11Y) :1627-1636
[2]  
FUJITA T, 2000, FUSION ENERGY 2000 P
[3]   Understanding and control of transport in Advanced Tokamak regimes in DIII-D [J].
Greenfield, CM ;
DeBoo, JC ;
Luce, TC ;
Stallard, BW ;
Synakowski, EJ ;
Baylor, LR ;
Burrell, KH ;
Casper, TA ;
Doyle, EJ ;
Ernst, DR ;
Ferron, JR ;
Gohil, P ;
Groebner, RJ ;
Lao, LL ;
Makowski, M ;
McKee, GR ;
Murakami, M ;
Petty, CC ;
Pinsker, RI ;
Politzer, PA ;
Prater, R ;
Rettig, CL ;
Rhodes, TL ;
Rice, BW ;
Schmidt, GL ;
Staebler, GM ;
Strait, EJ ;
Thomas, DM ;
Wade, MR .
PHYSICS OF PLASMAS, 2000, 7 (05) :1959-1967
[4]  
GRISHAM LR, 2000, FUSION ENERGY 2000 P
[5]   Stationary H-mode discharges with internal transport barrier on ASDEX upgrade [J].
Gruber, O ;
Wolf, RC ;
Dux, R ;
Fuchs, C ;
Günter, S ;
Kallenbach, A ;
Lackner, K ;
Maraschek, M ;
McCarthy, PJ ;
Meister, H ;
Pereversev, G ;
Ryter, F ;
Schweinzer, J ;
Seidel, U ;
Sesnic, S ;
Stäbler, A ;
Stober, J .
PHYSICAL REVIEW LETTERS, 1999, 83 (09) :1787-1790
[6]  
HAMAMATSU K, IN PRESS FUSION TECH
[7]  
HATAE T, 2001, FUSION ENERGY 2000 P
[8]   Latest progress in steady state plasma research on the Japan Atomic Energy Research Institute Tokamak-60 Upgrade [J].
Ide, S .
PHYSICS OF PLASMAS, 2000, 7 (05) :1927-1934
[9]  
IKEDA Y, 2000, FUSION ENERGY 2000 P
[10]  
ISAYAMA A, 2000, FUSION ENERGY 2000 P