Study of Current Profile Evolution in Presence of Tearing Modes in DIII-D Hybrid Discharges
Conference
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OSTI ID:15014363
An intermediate regime for tokamak operation has been obtained in DIII-D and in other tokamaks in which the inductive flux consumption is reduced and a broad current profile with the safety factor just above or near the sawtoothing limit is obtained and maintained. The DIII-D tokamak was operated in this regime near the no-wall b limit. High stability and good confinement was achieved at a desired level of q{sub 95} {approx} 3 to 4 for durations as long as 35{tau}{sub E}, three times the current-diffusion time. This regime offers the promise of achieving higher fusion gain and yield and/or longer burn duration for ITER.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 15014363
- Report Number(s):
- UCRL-CONF-204947; TRN: US0801192
- Resource Relation:
- Conference: Presented at: 31st EPS on Plasma Physics, London, United Kingdom, Jun 28 - Jul 02, 2004
- Country of Publication:
- United States
- Language:
- English
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