Tokamak: Difference between revisions
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A tokamak is a magnetic confinement device in which the poloidal component of the magnetic field is generated mainly by currents flowing in the plasma. | A tokamak is a [[Magnetic confinement|magnetic confinement]] device in which the poloidal component of the magnetic field is generated mainly by currents flowing in the plasma. | ||
The relative simplicity of the tokamak design has led to an initial headway of this design with respect to other prospective designs for a [[Nuclear fusion|fusion]] reactor, and the top performance among current fusion experiments has been achieved in tokamaks. As a consequence, next-step devices are based on this design. | The relative simplicity of the tokamak design has led to an initial headway of this design with respect to other prospective designs for a [[Nuclear fusion|fusion]] reactor, and the top performance among current fusion experiments has been achieved in tokamaks. As a consequence, next-step devices are based on this design. | ||
However, the intrinsic limitations of tokamaks when operated at high values of the operational parameters may lead to an eventual preference for the [[Stellarator reactor|stellarator]] design, in spite of its increased complexity. | However, the intrinsic limitations of tokamaks when operated at high values of the operational parameters may lead to an eventual preference for the [[Stellarator reactor|stellarator]] design, in spite of its increased complexity. | ||
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* [[:Wikipedia:Electric Tokamak|Electric Tokamak]] (USA) | * [[:Wikipedia:Electric Tokamak|Electric Tokamak]] (USA) | ||
* LT-1 (Australia) | * LT-1 (Australia) | ||
* [[:Wikipedia:Mega_Ampere_Spherical_Tokamak|MAST]] (Culham, UK) | |||
* PBX-M (Princeton, NJ, USA) | * PBX-M (Princeton, NJ, USA) | ||
* RTP (Rijnhuizen, The Netherlands) | * RTP (Rijnhuizen, The Netherlands) | ||
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* T-15 (Russia) | * T-15 (Russia) | ||
* TEXT (USA) | * TEXT (USA) | ||
* [https://www.fz-juelich.de/en/iek/iek-4/forschung/textor TEXTOR] (Jülich, Germany) | |||
* [[:Wikipedia:TFTR|TFTR]] (USA) | * [[:Wikipedia:TFTR|TFTR]] (USA) | ||
* [[TJ-I]] (Spain) | * [[TJ-I]] (Spain) | ||
* Tokamak de Varennes (Canada) | * Tokamak de Varennes (Canada) | ||
* [[:Wikipedia:Tokamak à Chauffage Alfvén|Tokamak à Chauffage Alfvén]] (CH) | |||
== Operational tokamaks == | == Operational tokamaks == | ||
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* [[:Wikipedia:HT-7|HT-7]] (Hefei, China) | * [[:Wikipedia:HT-7|HT-7]] (Hefei, China) | ||
* [http://www.cfn.ist.utl.pt/eng/Prj_Tokamak_main.html ISTTOK] (Lisbon, Portugal) | * [http://www.cfn.ist.utl.pt/eng/Prj_Tokamak_main.html ISTTOK] (Lisbon, Portugal) | ||
* [ | * [[:Wikipedia:Joint_European_Torus|JET]] (UK - European) | ||
* [[:Wikipedia:JT-60|JT-60]] (Naka, Japan) | * [[:Wikipedia:JT-60|JT-60]] (Naka, Japan) | ||
* [[:Wikipedia:KSTAR|KSTAR]] (Daejon, South Korea) | * [[:Wikipedia:KSTAR|KSTAR]] (Daejon, South Korea) | ||
* [[: | * KTM (Kazakhstan) | ||
* [[:Wikipedia:National Spherical Torus Experiment|NSTX]] (Princeton, NJ, USA) | * [http://plasma47.energy.kyoto-u.ac.jp/index_e.html LATE] Low Aspect ratio Torus Experiment (Kyoto, Japan) | ||
* [http://pst.pppl.gov/ltx/ LTX] Lithium Tokamak Experiment (USA) | |||
* [https://ccfe.ukaea.uk/research/mast-upgrade/ MAST Upgrade]] (Culham, UK) | |||
* [[:Wikipedia:National Spherical Torus Experiment|NSTX-U]] (Princeton, NJ, USA) | |||
* [https://www.dtu.dk/english/news/2019/08/dtus-own-tokamak-for-fusion-energy-research?id=69f514ed-2ad4-4a34-98a5-81e3d0ace6cd NORTH] (Copenhagen, Danemark) | |||
* [[:Wikipedia:Pegasus_Toroidal_Experiment|Pegasus]] (Madison, USA) | |||
* [http://plasma.usask.ca/storm/index.php STOR-M] (Canada) | * [http://plasma.usask.ca/storm/index.php STOR-M] (Canada) | ||
* T-10 (Russia) | * T-10 (Russia) | ||
* TCABR (Sao Paulo, Brazil - previously in Switzerland) | * TCABR (Sao Paulo, Brazil - previously in Switzerland) | ||
* [[:Wikipedia:Tokamak_%C3%A0_configuration_variable|TCV]] (Switzerland) | * [[:Wikipedia:Tokamak_%C3%A0_configuration_variable|TCV]] (Switzerland) | ||
* [[:Wikipedia:Tore Supra|Tore Supra]] (Cadarache, France) | * [[:Wikipedia:Tore Supra|Tore Supra]] (Cadarache, France) | ||
* VEST (Seoul, Korea) | |||
== Future tokamaks == | == Future tokamaks == | ||
* [[ITER]] (under construction, France - International) | * [[ITER]] (under construction, France - International) | ||
* [https://www.psfc.mit.edu/sparc SPARC] (USA) | |||
* [http://www.ipr.res.in/sst1/SST-1.html SST-1] (India) | * [http://www.ipr.res.in/sst1/SST-1.html SST-1] (India) | ||
* [[DEMO]] (in design phase) | * [[DEMO]] (in design phase) | ||
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== See also == | == See also == | ||
* [[Stellarator]] | |||
* [[:Wikipedia:Tokamak]] | * [[:Wikipedia:Tokamak]] | ||
* [http://www.tokamak.info www.tokamak.info] - comprehensive list of tokamaks | * [http://www.tokamak.info www.tokamak.info] - comprehensive list of tokamaks | ||
* [https://www.google.com/maps/d/viewer?mid=z74xNCoUPT3o.klOHFNk4lzac Map: All the world's tokamaks] | |||
Latest revision as of 14:15, 4 December 2023
A tokamak is a magnetic confinement device in which the poloidal component of the magnetic field is generated mainly by currents flowing in the plasma. The relative simplicity of the tokamak design has led to an initial headway of this design with respect to other prospective designs for a fusion reactor, and the top performance among current fusion experiments has been achieved in tokamaks. As a consequence, next-step devices are based on this design. However, the intrinsic limitations of tokamaks when operated at high values of the operational parameters may lead to an eventual preference for the stellarator design, in spite of its increased complexity.
Defunct tokamaks
- Alcator A (USA)
- Alcator C (USA)
- CASTOR (Prague, Czech Republic)
- Electric Tokamak (USA)
- LT-1 (Australia)
- MAST (Culham, UK)
- PBX-M (Princeton, NJ, USA)
- RTP (Rijnhuizen, The Netherlands)
- START (UK)
- T-3 (Russia)
- T-4 (Russia)
- T-15 (Russia)
- TEXT (USA)
- TEXTOR (Jülich, Germany)
- TFTR (USA)
- TJ-I (Spain)
- Tokamak de Varennes (Canada)
- Tokamak à Chauffage Alfvén (CH)
Operational tokamaks
- Aditya (Gujarat, India)
- Alcator C-Mod (Cambridge, USA)
- ASDEX Upgrade (Garching, Germany)
- COMPASS (Prague, Czech Republic - previously in Culham, UK)
- DIII-D (San Diego, USA)
- EAST (HT-7U) (Hefei, China)
- FTU (Frascati, Italy)
- HT-7 (Hefei, China)
- ISTTOK (Lisbon, Portugal)
- JET (UK - European)
- JT-60 (Naka, Japan)
- KSTAR (Daejon, South Korea)
- KTM (Kazakhstan)
- LATE Low Aspect ratio Torus Experiment (Kyoto, Japan)
- LTX Lithium Tokamak Experiment (USA)
- MAST Upgrade] (Culham, UK)
- NSTX-U (Princeton, NJ, USA)
- NORTH (Copenhagen, Danemark)
- Pegasus (Madison, USA)
- STOR-M (Canada)
- T-10 (Russia)
- TCABR (Sao Paulo, Brazil - previously in Switzerland)
- TCV (Switzerland)
- Tore Supra (Cadarache, France)
- VEST (Seoul, Korea)
Future tokamaks
See also
- Stellarator
- Wikipedia:Tokamak
- www.tokamak.info - comprehensive list of tokamaks
- Map: All the world's tokamaks