Recent results from the DIII-D tokamak
- General Atomics, San Diego, CA (United States)
The goal of the DIII-D program is to provide the integrated basis for commercially attractive steady state fusion power plants. Significant progress toward this goal has been achieved, enabled by system improvements including an error field correction coil, an expanded diagnostic set, a digital plasma control system, and high power rf systems. Simultaneous improvements in both the confinement and stability have been achieved during both VH-mode and negative central shear discharges. Fully non-inductive discharges with high bootstrap current fraction have been obtained. The divertor program has demonstrated simultaneous reduction of divertor heat flux and effective particle control using gas puffing and an in-vessel cryopump. Control of the wall particle inventory, He exhaust, and characterization of the scrapeoff layer and divertor plasma have been achieved. Progress has also been made in addressing additional specific needs for ITER: investigation of basic transport scaling, disruption characterization and avoidance, material erosion, and steady state beta limits.
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC03-89ER51114; W-7405-ENG-48; AC05-84OR21400; AC04-94AL85000; FG03-86ER53225; FG03-95ER54294
- OSTI ID:
- 505975
- Report Number(s):
- CONF-950905-; ISBN 0-7803-2970-8; TRN: 97:013668
- Resource Relation:
- Conference: 16. IEEE/NPSS symposium on fusion engineering, Champaign, IL (United States), 1-5 Oct 1995; Other Information: PBD: 1995; Related Information: Is Part Of 1995 IEEE 16. symposium on fusion engineering. Volume 1; Miley, G.H.; Elliott, C. [eds.] [Univ. of Illinois, Urbana, IL (United States). Fusion Studies Lab.]; PB: 886 p.
- Country of Publication:
- United States
- Language:
- English
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