Stellarator: Difference between revisions

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== Operational stellarators ==
== Operational stellarators ==
* [http://fusion.auburn.edu/ CAT/CTH] (Auburn, USA)
* [http://prl.anu.edu.au/H-1NF H-1NF] (Australia)
* Heliotron-J (Kyoto, Japan)
* [http://www.hsx.wisc.edu/ HSX] (USA)
* [http://www.lhd.nifs.ac.jp/en/ LHD] (Japan)
* [http://www.lhd.nifs.ac.jp/en/ LHD] (Japan)
* [[TJ-II]] (Spain)
* [[TJ-II]] (Spain)
* [http://www.hsx.wisc.edu/ HSX] (USA)
* [http://prl.anu.edu.au/H-1NF H-1NF] (Australia)
* [http://www.ipf.uni-stuttgart.de/gruppen/pdd/pdd_tjk.html TJ-K] (Germany) - formerly [[TJ-IU]]
* [http://www.ipf.uni-stuttgart.de/gruppen/pdd/pdd_tjk.html TJ-K] (Germany) - formerly [[TJ-IU]]
* [http://www.ipp.mpg.de/ippcms/eng/for/bereiche/e3/projekte/wega.html WEGA] (Germany)
* [http://www.ipp.mpg.de/ippcms/eng/for/bereiche/e3/projekte/wega.html WEGA] (Germany)
* [http://fusion.auburn.edu/ CAT/CTH] (Auburn, USA)
* [http://www.fusionvic.org/ UST-1] (Spain, tabletop)
* [http://www.fusionvic.org/ UST-1] (Spain, tabletop)



Revision as of 13:55, 23 October 2009

A stellarator is a magnetic confinement device. The rotational transform is predominantly generated by external coils - as opposed to a tokamak, in which the poloidal field is generated by plasma currents. Hybrid concepts employ both external coils and self-generated (bootstrap) currents (e.g. NCSX).

NCSX plasma vessel.

Defunct stellarators

  • ATF (USA)
  • W7-AS (Germany, 1988-2002)
  • CHS (Japan)
  • NCSX (USA, cancelled before construction was completed)

Operational stellarators

Future stellarators

  • W7-X (under construction, Germany)
  • QPS (in design phase, USA)

See also