DocumentCode :
2758532
Title :
DIII-D: Recent Physics Results, Implemented and Planned Hardware Upgrades
Author :
Petersen, P.I.
Author_Institution :
Gen. Atomics, San Diego, CA
fYear :
2005
fDate :
Sept. 2005
Firstpage :
1
Lastpage :
7
Abstract :
During the last two years, the DIII-D tokamak has been operated for a total of 34 run weeks, during which significant advances have been achieved in many areas of plasma physics. This progress was only possible because of the improvements in the tools available to the DIII-D program to control and manipulate the plasma core and edge conditions. The important systems in this effort include the electron cyclotron (EC) system, the fast wave system (restarted after being sidelined for four years), 12 new internal coils, an upgraded plasma control system and a comprehensive set of turbulence diagnostics. The EC system\´s versatility was demonstrated by the various roles it played in the physics research program. It was used as a probe to demonstrate the "hybrid" plasmas are regulated by m/n=3/2 tearing modes, it was used to suppress the m/n=2/1 Neoclassical Tearing Mode, which allowed the plasma pressure to be raised to new heights, and in an active feedback mode EC power was used to control the q-profile using real-time equilibrium reconstructions based upon motional Stark effect data. The fast wave system was used in conjunction with the EC system for current profile experiments. The internal control coil system was used to investigate suppression of the resistive wall modes and reduction and/or elimination of ELMs. During this year, the DIII-D facility will implement major changes and upgrades to expand the frontiers in several of the areas of tokamak plasma physics research. One of the four neutral beams will be rotated from the co-to the counter-injection mode so that heated plasmas with little or no rotation can be studied. The present lower divertor will be removed and a new extended shelf divertor will be installed to provide the capability of pumping high triangular double null plasmas. Three new long pulse one MW class gyrotron systems will be brought on line, which will double the long pulse capability of the EC system. Two of the three aging cooling towers wi- ll be replaced with two new high efficiency towers that can handle the higher heat loads expected in the future from 10 s pulse operation. These and other improvements to the facility will be discussed and presented
Keywords :
Tokamak devices; fusion reactor divertors; fusion reactor ignition; fusion reactor instrumentation; fusion reactor operation; gyrotrons; plasma beam injection heating; plasma diagnostics; plasma hybrid waves; plasma pressure; plasma turbulence; DIII-D tokamak; MW class gyrotron systems; active feedback mode; aged cooling towers; counter-injection mode; current profile experiments; electron cyclotron system; fast wave system; hardware upgrades; heated plasmas; high triangular double null plasmas; hybrid plasmas; internal control coil system; long pulse capability; lower divertor; motional Stark effect; neoclassical tearing mode; neutral beam injection; plasma core; plasma pressure; real-time equilibrium reconstructions; resistive wall modes; shelf divertor; tokamak plasma physics research; turbulence diagnostics; upgraded plasma control system; Coils; Control systems; Cyclotrons; Electrons; Hardware; Physics; Plasma diagnostics; Plasma waves; Poles and towers; Tokamaks; hardware upgrades; physics results; tokamak;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
Conference_Location :
Knoxville, TN
Print_ISBN :
0-4244-0150-X
Electronic_ISBN :
0-4244-0150-X
Type :
conf
DOI :
10.1109/FUSION.2005.252852
Filename :
4018886
Link To Document :
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