Stellarator: Difference between revisions

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* [http://www.ipp.mpg.de/ippcms/eng/for/bereiche/e3/projekte/w7as.html W7-AS] (Germany, 1988-2002)
* [http://www.ipp.mpg.de/ippcms/eng/for/bereiche/e3/projekte/w7as.html W7-AS] (Germany, 1988-2002)
* [[CHS]] (Japan)
* [[CHS]] (Japan)
* [[NCSX]] (USA, cancelled before construction was completed)
* [http://ncsx.pppl.gov/ NCSX] (USA, cancelled before construction was completed)


== Operational stellarators ==
== Operational stellarators ==
* [[LHD]] (Japan)
* [http://www.lhd.nifs.ac.jp/en/ LHD] (Japan)
* [[TJ-II]] (Spain)
* [[TJ-II]] (Spain)
* [[HSX]] (USA)
* [http://www.hsx.wisc.edu/ HSX] (USA)
* [[H-1NF]] (Australia)
* [http://prl.anu.edu.au/H-1NF H-1NF] (Australia)
* [[TJ-K]] (Germany) - formerly [[TJ-IU]]
* [[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)
* [[CAT]] (Auburn, USA)
* [http://fusion.auburn.edu/ CAT/CTH] (Auburn, USA)
* [[UST-1]] (Spain, tabletop)
* [[UST-1]] (Spain, tabletop)



Revision as of 08:07, 23 October 2009

A stellarator is a magnetic confinement device. The rotational transform is predominantly generated by external coils - differently to tokamaks for which the poloidal field is generated by plasma currents. Hybrid concepts employ both external coils and self-generated (boot-strap) currents. An example is 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