Tungsten limiter tests in ASDEX Upgrade

  • M. Y. Ye
  • , H. Maier
  • , A. Herrmann
  • , V. Rohde
  • , H. Bolt
  • , R. Neu
  • , J. Neuhauser

Research output: Contribution to journalArticlepeer-review

7 Scopus citations

Abstract

In order to prepare for tungsten coating to be applied to the low field side poloidal guard limiters, 1 μm W-coated CFC limiter tests have been performed in ASDEX Upgrade. The test limiters were exposed to H-mode deuterium plasmas with the neutral beam heating at maximum 5 MW for approximately 1 s. The power flux deposited on the test limiter was calculated by solving the 3-D heat conduction equation by using the measured time dependent surface temperatures as boundary conditions. The experimental results show that the heating with more radial NI beams leads to a higher local deposited power with a longer radial decay length related to banana particle loss. Strong localized W erosion was found at the tip of the test limiter due to arcing, which obviously depends on the neutral beam injection (NBI) geometry.

Original languageEnglish
Pages (from-to)104-108
Number of pages5
JournalJournal of Nuclear Materials
Volume337-339
Issue number1-3 SPEC. ISS.
DOIs
StatePublished - 1 Mar 2005
Externally publishedYes

Keywords

  • ASDEX Upgrade
  • Erosion
  • Poloidal limiter
  • Power flux
  • Tungsten coated carbon

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