Abstract
The low recycling regime, although never considered as an option for ITER, may suggest a solution to its important issues, such as edge localized modes, plasma and particle control, tritium inventory, damage of plasma facing components and dust accumulation, in a way consistent with both the ITER mission (including the ignition) and its baseline design and safety. Such a regime can be approached using liquid lithium surfaces efficiently pumping hydrogen isotopes. An active area of about 40 m2, covered by ≃0.1 mm thick lithium, which is replenished with the rate of 10 kg/h would be capable of absorption of plasma D and T particles and at the same time consistent with the ITER limitations regarding lithium. For low recycling conditions, a new consideration is outlined for the helium ash pumping problem.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 453-457 |
| Number of pages | 5 |
| Journal | Journal of Nuclear Materials |
| Volume | 363-365 |
| Issue number | 1-3 |
| DOIs | |
| State | Published - Jun 15 2007 |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- General Materials Science
- Nuclear Energy and Engineering
Keywords
- Divertor material
- Lithium
- Recycling
- Wall pumping
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