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ITER: Difference between revisions
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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 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]]. | ||
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== Main specifications == | == Main specifications == | ||
ITER is a magnetic confinement device of the tokamak type, with the following characteristics: | ITER is a magnetic confinement device of the tokamak type, with the following characteristics in the reference scenario: | ||
<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> | ||
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!''Parameter'' !!''Value'' | !''Parameter'' !!''Value'' | ||
|- | |- | ||
|Major radius, R<sub>0</sub>|| | |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 | |||
|- | |||
|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 | |||
|- | |||
|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 electron temperature, <T<sub>e</sub>> (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 | |||
|- | |||
|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 | |||
|} | |} | ||
== See also == | |||
* [http://www.iter.org ITER website] | |||
== References == | == References == | ||
<references /> | <references /> | ||