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Low recycling regime in ITER and the LiWall concept for its divertor

  • L. E. Zakharov
  • , W. Blanchard
  • , R. Kaita
  • , H. Kugel
  • , R. Majeski
  • , J. Timberlake

Research output: Contribution to journalArticlepeer-review

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 languageEnglish (US)
Pages (from-to)453-457
Number of pages5
JournalJournal of Nuclear Materials
Volume363-365
Issue number1-3
DOIs
StatePublished - 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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