Divertor research on the DIII-D tokamak
- Lawrence Livermore National Lab., CA (United States)
- General Atomics, San Diego, CA (United States); and others
In this paper the authors summarize recent progress on DIII-D in developing techniques for divertor power and particle control relevant to next generation tokamaks such as the proposed ITER and TPX devices. Density control and helium removal by divertor pumping have been demonstrated for the first time in high confinement ELMing H-mode discharges ({tau} {approximately} 2 {times} {tau}{sub ITER-89P}) following installation of a divertor cryopumping system. The peak divertor heat flux in similar H-mode discharges has been reduced through production of a radiating mantle with neon or argon puffing (reductions of 3--5). A number of diagnostics have been added to improve the understanding of the physical processes involved. They are now designing modified double-null divertor structures for DIII-D that will provide improved particle control for high-triangularity VH-mode plasmas while at the same time allowing for gas puffing to reduce the divertor heat flux.
- Research Organization:
- General Atomics, San Diego, CA (United States); Oak Ridge National Lab., TN (United States); Sandia National Labs., Albuquerque, NM (United States); California Univ., Los Angeles, CA (United States). Dept. of Physics; California Univ., Los Angeles, CA (United States); Lawrence Livermore National Lab., CA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC03-89ER51114; AC05-84OR21400; AC04-94AL85000; FG03-89ER51121; FG03-86ER53225; W-7405-ENG-48
- OSTI ID:
- 10104522
- Report Number(s):
- GA-A-21851; IAEA-CN-60/A-4-I-2; CONF-940933-21; ON: DE95003942; TRN: AHC29503%%112
- Resource Relation:
- Conference: 15. international conference on plasma physics and controlled nuclear fusion research,Madrid (Spain),26 Sep - 1 Oct 1994; Other Information: PBD: Oct 1994
- Country of Publication:
- United States
- Language:
- English
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