Development of a tokamak plasma optimized for stability and confinement

Journal Article · Sat Apr 01 04:00:00 EST 1995 · Fusion Technology

OSTI ID:219751

Politzer, P A ^[1]

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1. General Atomics, San Diego, CA (United States)

The DIII-D advanced tokamak development program is directed toward developing an understanding of the characteristics which lead to high stability and confinement, and to use that understanding to demonstrate stationary, high performance operation through active control of the plasma shape and profiles. We have identified some of the features of the operating modes in DIII-D that contribute to better performance. These are control of the plasma shape, control of both bulk plasma rotation and shear in the rotation and E{sub r} profiles, and particularly control of the toroidal current profiles. In order to guide our future experiments, we are developing optimized scenarios based on our anticipated plasma control capabilities, particularly using fast wave current dive (on-axis) and electron cyclotron current drive (off-axis). The most highly developed model is the second-stable core VH-mode, which has a reversed magnetic shear safety factor profile [q(0)=3.9, q{sub min}=2.6, and q{sub 95}=6]. This model plasma uses profiles which we expect to be realizable. At {Beta}{sub N} >= 6, it is stable to n=1 kink modes and ideal ballooning modes, and is expected to reach H >= 3 with VH-mode-like confinement. 23 refs., 11 figs.

• DOE Contract Number: AC05-84OR21400; AC03-89ER51114; W-7405-ENG-48
• OSTI ID: 219751
• Report Number(s): CONF-941182--
• Journal Information: Fusion Technology, Journal Name: Fusion Technology Vol. 27; ISSN 0748-1896; ISSN FUSTE8
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BALLOONING INSTABILITY
BOOTSTRAP CURRENT
DESIGN
DIVERTORS
OPTIMIZATION
PERFORMANCE
PLASMA CONFINEMENT
STABILITY
TEMPERATURE DISTRIBUTION
THERMONUCLEAR REACTORS
TOKAMAK DEVICES