4,380
edits
ITER: Difference between revisions
→See also
No edit summary |
|||
| (11 intermediate revisions by the same user not shown) | |||
| Line 1: | Line 1: | ||
ITER is an international engineering and research project oriented towards demonstrating the technical and scientific viability of [[Nuclear fusion|fusion as an energy source]]. | ITER is an international engineering and research project oriented towards demonstrating the technical and scientific viability of [[Nuclear fusion|fusion as an energy source]]. | ||
For general background information on the project, refer to the [[:Wikipedia:ITER|Wikipedia]]. | For general background information on the project, refer to the [[:Wikipedia:ITER|Wikipedia]]. | ||
| Line 5: | Line 4: | ||
== 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 [[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> | ||
<ref>[http://dx.doi.org/10.1088/0741-3335/47/5A/003 A.C.C. Sips et al, ''Advanced scenarios for ITER operation'', Plasma Phys. Control. Fusion '''47''' (2005) A19-A40]</ref> | <ref>[http://dx.doi.org/10.1088/0741-3335/47/5A/003 A.C.C. Sips et al, ''Advanced scenarios for ITER operation'', Plasma Phys. Control. Fusion '''47''' (2005) A19-A40]</ref> | ||
[[File:ITER.jpg|400px|thumb|right|ITER design]] | |||
{| class="wikitable" align="center" border="1" | {| class="wikitable" align="center" border="1" | ||
| Line 25: | Line 26: | ||
|Confinement enhancement, H<sub>H98</sub>(y,2) || 1.0 | |Confinement enhancement, H<sub>H98</sub>(y,2) || 1.0 | ||
|- | |- | ||
|Normalised beta, β<sub>N</sub> || 1.8 | |[[Beta|Normalised beta]], β<sub>N</sub> || 1.8 | ||
|- | |- | ||
|Average electron density, <n<sub>e</sub>> (10<sup>19</sup>m<sup>-3</sup>) || 10.1 | |Average electron density, <n<sub>e</sub>> (10<sup>19</sup>m<sup>-3</sup>) || 10.1 | ||
|- | |- | ||
|Fraction of Greenwald limit, <n<sub>e</sub>>/n<sub>GW</sub> || 0.85 | |Fraction of [[Greenwald limit]], <n<sub>e</sub>>/n<sub>GW</sub> || 0.85 | ||
|- | |- | ||
|Average ion temperature, <T<sub>i</sub>> (keV) || 8.0 | |Average ion temperature, <T<sub>i</sub>> (keV) || 8.0 | ||
| Line 41: | Line 42: | ||
|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 | ||
| Line 48: | Line 49: | ||
|} | |} | ||
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 == | ||
| Line 54: | Line 55: | ||
=== Organizational === | === Organizational === | ||
* Multiparty | * Multiparty coordination | ||
=== Technical === | === Technical === | ||
* Avoidance and control of | * 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 | ||
=== Scientific === | === Scientific === | ||
| Line 68: | Line 68: | ||
* Advanced operational scenarios (cf. [[Internal Transport Barrier]]) | * Advanced operational scenarios (cf. [[Internal Transport Barrier]]) | ||
* Alpha and energetic particle physics | * Alpha and energetic particle physics | ||
* Diagnostic development | |||
== See also == | == See also == | ||
| Line 73: | Line 74: | ||
* [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]] | |||