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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]]. | ||
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<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" | ||
Revision as of 19:02, 6 September 2009
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]
| 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 mag be achieved, e.g., by creating Internal Transport Barriers.
Challenges
Organizational
- Multiparty co-ordination
Technical
- Avoidance and control of MHD disruptions
- ELM mitigation
- Heat load handling in the divertor and on the wall
- Radiation handling and wall materials
- Diagnostic development
Scientific
- Advanced operational scenarios (cf. Internal Transport Barrier)
- Alpha and energetic particle physics