View source for ITER

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]].

== Main specifications ==

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/10.1088/0741-3335/47/5A/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"
!''Parameter'' !!''Value''
|-
|Major radius, R<sub>0</sub> (m) || 6.2
|-
|Minor radius, a (m) || 2.0 
|-
|Toroidal field at R<sub>0</sub>, B<sub>T</sub> (T) || 5.3 
|-
|Plasma current, I<sub>p</sub> (MA) || 15 
|-
|Edge safety factor, q<sub>95</sub> || 3.0 
|-
|Confinement enhancement, H<sub>H98</sub>(y,2) || 1.0 
|-
|[[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 
|-
|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 electron temperature, &lt;T<sub>e</sub>&gt; (keV) || 8.8 
|-
|Neutral beam power, P<sub>NB</sub> (MW) || 33 
|-
|RF power, P<sub>RF</sub> (MW) || 7
|-
|Fusion power, P<sub>fusion</sub> (MW) || 400 
|-
|[[: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 
|-
|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 ==

* [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 />

[[Category:Toroidal confinement devices]]