A review of recent experiments on W and high Z materials as plasma-facing components in magnetic fusion devices

Nobuaki Noda, Volker Philipps, Rudolf Neu

Research output: Contribution to journalArticlepeer-review

9 Scopus citations

Abstract

Since the 10th PSI conference in 1992, high Z refractory metals have been attracting growing interest as candidates for plasma facing materials, because of their resistance against erosion. In tokamaks such as TEXTOR, ASDEX Upgrade, FTU, Alcator C-Mod, D III-D, considerable effort has been made to study the behavior of high Z impurity in the core and edge plasmas, erosion/re-deposition processes at the limiter/divertor surfaces, hydrogen isotope retention, material development and tests, etc. An interim review of these studies is given. Tentative conclusions are drawn in order to gel a view and direction in the future studies.

Original languageEnglish
Pages (from-to)227-243
Number of pages17
JournalJournal of Nuclear Materials
Volume241-243
DOIs
StatePublished - 11 Feb 1997
Externally publishedYes

Keywords

  • Erosion and particle deposition
  • High Z wall material
  • Impurity source
  • Impurity transport
  • Tritium inventory

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