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ITER: Difference between revisions
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== Main specifications == | == Main specifications == | ||
ITER is a magnetic confinement device of the tokamak type. | ITER is a magnetic confinement device of the [[Tokamak|tokamak]] type. | ||
The reference operational scenario is the ELMy [[H-mode]] with the following characteristic parameters: | The reference operational scenario is the ELMy [[H-mode]] with the following characteristic parameters: | ||
<ref>[http://dx.doi.org/10.1088/0741-3335/44/5/304 R. Aymar et al, ''The ITER design'', Plasma Phys. Control. Fusion '''44''' (2002) 519-565]</ref> | <ref>[http://dx.doi.org/10.1088/0741-3335/44/5/304 R. Aymar et al, ''The ITER design'', Plasma Phys. Control. Fusion '''44''' (2002) 519-565]</ref> | ||
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|Fusion power, P<sub>fusion</sub> (MW) || 400 | |Fusion power, P<sub>fusion</sub> (MW) || 400 | ||
|- | |- | ||
|Fusion gain, Q=P<sub>fusion</sub>/(P<sub>NB</sub>+P<sub>RF</sub>) || 10 | |[[:Wikipedia:Fusion_energy_gain_factor|Fusion gain]], Q=P<sub>fusion</sub>/(P<sub>NB</sub>+P<sub>RF</sub>) || 10 | ||
|- | |- | ||
|Non inductive current fraction, I<sub>NI</sub>/I<sub>p</sub> (%) || 28 | |Non inductive current fraction, I<sub>NI</sub>/I<sub>p</sub> (%) || 28 | ||
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|} | |} | ||
In the standard scenario, part of the plasma current is inductively driven, so that operation is not steady state. Advanced scenarios seek to maximize pulse length by making use of the [[Bootstrap current|bootstrap current]]. This | In the standard scenario, part of the plasma current is inductively driven, so that operation is not steady state. Advanced scenarios seek to maximize pulse length by making use of the [[Bootstrap current|bootstrap current]]. This may be achieved, e.g., by creating [[Internal Transport Barrier|Internal Transport Barriers]]. | ||
== Challenges == | == Challenges == | ||
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=== Organizational === | === Organizational === | ||
* Multiparty | * Multiparty coordination | ||
=== Technical === | === Technical === | ||
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* Avoidance and control of [[Disruption|disruptions]] | * Avoidance and control of [[Disruption|disruptions]] | ||
* [[Edge Localized Modes|ELM]] mitigation | * [[Edge Localized Modes|ELM]] mitigation | ||
* Heat load handling in the divertor and on the wall | * Heat load handling in the [[Divertor|divertor]] and on the wall | ||
* Radiation handling and wall materials | * Radiation handling and wall materials | ||
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* [http://www.iter.org ITER website] | * [http://www.iter.org ITER website] | ||
* [http://www.efda.org/the_iter_project/index.htm EFDA: ITER] | * [http://www.efda.org/the_iter_project/index.htm EFDA: ITER] | ||
* [http:// | * [http://iopscience.iop.org/0029-5515/39/12 ''ITER Physics Basis'', Nucl. Fusion '''39''', 12 (1999)] | ||
== References == | == References == | ||
<references /> | <references /> | ||
[[Category:Toroidal confinement devices]] | |||