Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET

Tutkimustuotos: Lehtiartikkelivertaisarvioitu

Tutkijat

  • G.J. van Rooij
  • J.W. Coenen
  • L. Aho-Mantila
  • S. Brezinsek
  • M. Clever
  • R. Dux
  • M. Groth
  • K. Krieger
  • S. Marsen
  • G.F. Matthews
  • A.G. Meigs
  • R. Neu
  • S. Potzel
  • T. Puetterich
  • J. Rapp
  • M.F. Stamp
  • ASDEX Upgrade team
  • JET-EFDA Contributors

Organisaatiot

  • Culham Science Centre
  • EURATOM-FOM
  • Jülich Research Centre
  • VTT Technical Research Centre of Finland
  • Max-Planck-Institut für Plasmaphysik
  • Oak Ridge National Laboratory

Kuvaus

Tungsten erosion in the outer divertor of the JET ITER like wall was quantified by spectroscopy. Effective sputtering yields of typically 10 (4) were measured in L-mode at similar to 30 eV attached divertor conditions and beryllium was identified as the main cause of sputtering. The signature of prompt redeposition was observed in the analysis of WI 400.9 nm and WII 364 nm line ratios and indicative of >50% redeposition fractions. Inter- and intra-ELM sputtering were compared for an example of 10 Hz ELMs with 13 MW NBI heating, in which intra-ELM sputtering was found to dominate by a factor of 5. Nitrogen seeding initially increased the tungsten sputtering threefold due to higher extrinsic impurity levels and effectively reduced the tungsten sputtering when the divertor plasma temperature was decreased from the initial 25 eV down to 15 eV. (C) 2013 Euratom. Published by Elsevier B.V. All rights reserved.

Yksityiskohdat

AlkuperäiskieliEnglanti
SivutS42-S47
Sivumäärä6
JulkaisuJournal of Nuclear Materials
Vuosikerta438
TilaJulkaistu - heinäkuuta 2013
OKM-julkaisutyyppiA1 Julkaistu artikkeli, soviteltu

ID: 753943