Oxidation wall conditionings on HT-7 and EAST superconducting tokamaks

  • J. S. Hu
  • , J. G. Li
  • , Y. P. Zhao

Research output: Contribution to journalArticlepeer-review

2 Scopus citations

Abstract

Oxidation treatment is one of the most promising methods for amorphous tritiated carbon layers removal, which is important for tritium removal for ITER. A series of experiments of oxidation wall conditioning, including thermo-oxidation, glow discharge (O-GDC) and radio frequency wave associated oxidation (O-ICR), were carried out in a limiter machine - HT-7 with 20% carbon walls, and in an ITER-relevant full superconducting tokamak - EAST with metal walls or full carbon walls for divertor configuration. This paper will give a review of the oxidation wall conditionings on HT-7 and EAST.

Original languageEnglish
Pages (from-to)S1054-S1057
JournalJournal of Nuclear Materials
Volume415
Issue number1 SUPPL
DOIs
StatePublished - 1 Aug 2011

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