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[[File:ITER.jpg|400px|thumb|right|ITER design]]
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 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]].


== Main specifications ==
== Main specifications ==


ITER is a magnetic confinement device of the tokamak type, with the following characteristics in the reference scenario:
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:
<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"
!''Parameter'' !!''Value''
!''Parameter'' !!''Value''
|-
|-
|Major radius, R<sub>0</sub>(m) || 6.2
|Major radius, R<sub>0</sub> (m) || 6.2
|-
|-
|Minor radius, a (m) || 2.0  
|Minor radius, a (m) || 2.0  
Line 24: Line 26:
|Confinement enhancement, H<sub>H98</sub>(y,2) || 1.0  
|Confinement enhancement, H<sub>H98</sub>(y,2) || 1.0  
|-
|-
|Normalised beta, &beta;<sub>N</sub> || 1.8  
|[[Beta|Normalised beta]], &beta;<sub>N</sub> || 1.8  
|-
|-
|Average electron density, &lt;n<sub>e</sub>&gt; (10<sup>19</sup>m<sup>-3</sup>) || 10.1  
|Average electron density, &lt;n<sub>e</sub>&gt; (10<sup>19</sup>m<sup>-3</sup>) || 10.1  
|-
|-
|Fraction of Greenwald limit, &lt;n<sub>e</sub>&gt;/n<sub>GW</sub> || 0.85  
|Fraction of [[Greenwald limit]], &lt;n<sub>e</sub>&gt;/n<sub>GW</sub> || 0.85  
|-
|-
|Average ion temperature, &lt;T<sub>i</sub>&gt; (keV) || 8.0  
|Average ion temperature, &lt;T<sub>i</sub>&gt; (keV) || 8.0  
Line 40: 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 46: Line 48:
|Burn time (s) || 400  
|Burn time (s) || 400  
|}
|}
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 ==
=== Organizational ===
* Multiparty coordination
=== Technical ===
* Avoidance and control of [[Disruption|disruptions]]
* [[Edge Localized Modes|ELM]] mitigation
* Heat load handling in the [[Divertor|divertor]] and on the wall
* Radiation handling and wall materials
=== Scientific ===
* Advanced operational scenarios (cf. [[Internal Transport Barrier]])
* Alpha and energetic particle physics
* Diagnostic development


== See also ==
== See also ==


* [http://www.iter.org ITER website]
* [http://www.iter.org ITER website]
* [http://www.efda.org/the_iter_project/index.htm EFDA: ITER]
* [http://iopscience.iop.org/0029-5515/39/12 ''ITER Physics Basis'', Nucl. Fusion '''39''', 12 (1999)]


== References ==
== References ==
<references />
<references />
[[Category:Toroidal confinement devices]]

Latest revision as of 11:28, 19 August 2012

ITER is an international engineering and research project oriented towards demonstrating the technical and scientific viability of fusion as an energy source. For general background information on the project, refer to the Wikipedia.

Main specifications

ITER is a magnetic confinement device of the tokamak type. The reference operational scenario is the ELMy H-mode with the following characteristic parameters: [1] [2]

ITER design
Parameter Value
Major radius, R0 (m) 6.2
Minor radius, a (m) 2.0
Toroidal field at R0, BT (T) 5.3
Plasma current, Ip (MA) 15
Edge safety factor, q95 3.0
Confinement enhancement, HH98(y,2) 1.0
Normalised beta, βN 1.8
Average electron density, <ne> (1019m-3) 10.1
Fraction of Greenwald limit, <ne>/nGW 0.85
Average ion temperature, <Ti> (keV) 8.0
Average electron temperature, <Te> (keV) 8.8
Neutral beam power, PNB (MW) 33
RF power, PRF (MW) 7
Fusion power, Pfusion (MW) 400
Fusion gain, Q=Pfusion/(PNB+PRF) 10
Non inductive current fraction, INI/Ip (%) 28
Burn time (s) 400

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. This may be achieved, e.g., by creating Internal Transport Barriers.

Challenges

Organizational

  • Multiparty coordination

Technical

  • Avoidance and control of disruptions
  • ELM mitigation
  • Heat load handling in the divertor and on the wall
  • Radiation handling and wall materials

Scientific

See also

References

  1. ↑ R. Aymar et al, The ITER design, Plasma Phys. Control. Fusion 44 (2002) 519-565
  2. ↑ A.C.C. Sips et al, Advanced scenarios for ITER operation, Plasma Phys. Control. Fusion 47 (2005) A19-A40
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