Noninductive Current Drive and Steady-State Operation in JT-60U
Journal Article
·
· Fusion Science and Technology
OSTI ID:20845852
Studies on noninductive current drive (CD) and development of an integrated steady-state high performance operation in JT-60 are reviewed. Experiments on lower hybrid current drive (LHCD) in JT-60 have shown a large noninductive current up to 3.6 MA, high current drive efficiency of 3.5 x 10{sup 19} m{sup -2}A/W, and a flexible current profile control. Basic studies on LH waves, such as an effect of accessibility condition, fast electron behaviors, and so on, in JT-60 have contributed to understanding LHCD physics. Significant progress in neutral beam current drive (NBCD) has been made in JT-60 by testing the performance of negative ion-based (N) neutral beam injection (NBI) (N-NBI). The CD efficiency of {approx}1.5 x 10{sup 19} m{sup -2}A/W and negative ion-based neutral beam (N-NB) driven current of {approx}1 MA have been demonstrated in N-NBCD. Strongly localized noninductive driven current by electron cyclotron current drive (ECCD) was identified with a fundamental O-mode scheme from a low field side injection. ECCD in JT-60 has shown CD efficiency of 0.5 x 10{sup 19} m{sup -2}A/W and EC-driven current of 0.2 MA. Modification of local current profile was demonstrated and was used for suppression of neoclassical tearing mode. Based on these developments, two integrated steady-state operation scenarios were developed in JT-60, which are reversed magnetic shear (R/S) plasmas and high {beta}p ELMy H-mode. In these operation regimes, discharges have been sustained near the steady-state current profile under full noninductive current drive (High {beta}p; HH{sub y2} {approx} 1.4 and {beta}{sub N} {approx} 2.5 with N-NB, R/S; HH{sub y2} {approx} 2.2 and {beta}{sub N} {approx} 2 with f{sub BS} {approx} 80%). High performance plasmas with a high n{sub Do}{tau}{sub E}T{sub io} and at high normalized density were also produced under fully noninductive condition in high {beta}p ELMy H-mode and R/S mode.
- OSTI ID:
- 20845852
- Journal Information:
- Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 2,3 Vol. 42; ISSN 1536-1055
- Country of Publication:
- United States
- Language:
- English
Similar Records
High performance and current drive experiments in the JAERI Tokamak-60 Upgrade
Recent results and future prospects on the JT-60U tokamak
RF heating and current drive experiment on JT-60
Journal Article
·
Sun May 01 00:00:00 EDT 1994
· Physics of Plasmas; (United States)
·
OSTI ID:6690593
Recent results and future prospects on the JT-60U tokamak
Journal Article
·
Mon Oct 31 23:00:00 EST 1994
· Fusion Technology
·
OSTI ID:41434
RF heating and current drive experiment on JT-60
Conference
·
Tue Sep 01 00:00:00 EDT 1987
· AIP Conf. Proc.; (United States)
·
OSTI ID:7020508
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ANIONS
BEAM CURRENTS
ECR CURRENT DRIVE
EDGE LOCALIZED MODES
EFFICIENCY
ELECTRONS
H-MODE PLASMA CONFINEMENT
JT-60 TOKAMAK
JT-60U TOKAMAK
LOWER HYBRID CURRENT DRIVE
MAGNETIC FIELD CONFIGURATIONS
NEOCLASSICAL TRANSPORT THEORY
NEUTRAL ATOM BEAM INJECTION
PERFORMANCE
PLASMA
PLASMA DENSITY
REVERSED SHEAR
STEADY-STATE CONDITIONS
TEARING INSTABILITY
ANIONS
BEAM CURRENTS
ECR CURRENT DRIVE
EDGE LOCALIZED MODES
EFFICIENCY
ELECTRONS
H-MODE PLASMA CONFINEMENT
JT-60 TOKAMAK
JT-60U TOKAMAK
LOWER HYBRID CURRENT DRIVE
MAGNETIC FIELD CONFIGURATIONS
NEOCLASSICAL TRANSPORT THEORY
NEUTRAL ATOM BEAM INJECTION
PERFORMANCE
PLASMA
PLASMA DENSITY
REVERSED SHEAR
STEADY-STATE CONDITIONS
TEARING INSTABILITY