Recent DIII-D results
Recent experimental results from the DIII-D tokamak point in directions that could lead to a commercially attractive tokamak demonstration reactor concept, with enhanced confinement, stability, current drive, and diverter performance. These recent results include electric-field and plasma current profile control, noninductive current drive, and diverter power and particle control. Edge radial electric field shear suppresses edge turbulence and improves confinement in H-mode discharges. The electric field extends deeper into VH-mode plasmas and may explain the improved confinement. In VH-mode plasmas the fusion triple product has increased to n{sub D}(0) {tau}{sub E}T{sub i}(0) = 2 {times} 10{sup 20} m{sup {minus}3} s keV and the central electron temperature to 7 keV. Experiments with current profile control have shown improved confinement and stability, access to second stability, and the suppression of TAE, modes. Low power fast wave current drive experiments at the 1 MW power level have driven currents at the 0.1 MA level. Divertor experiments indicate that the modeling codes overestimate peak divertor power fluxes. With deuterium gas injection into the divertor, the peak diverter power flux has been reduced by a factor of 5. Edge localized modes (ELMs) are shown to purge helium from the core plasma to the diverter chamber where, in a reactor, the alpha ash could be pumped away.
- Research Organization:
- General Atomic Co., San Diego, CA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC03-89ER51114; W-7405-ENG-48; FG03-89ER51121; AC05-84OR21400
- OSTI ID:
- 10115310
- Report Number(s):
- GA-A-21089; CONF-920913-25; ON: DE93004468
- Resource Relation:
- Conference: 14. international conference on plasma physics and controlled nuclear fusion research,Wurzburg (Germany),30 Sep - 7 Oct 1992; Other Information: PBD: Oct 1992
- Country of Publication:
- United States
- Language:
- English
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