Thermal management of tungsten leading edges in DIII-D

R. E. Nygren, D. L. Rudakov, C. Murphy, J. D. Watkins, E. A. Unterberg, J. L. Barton, P. C. Stangeby

Research output: Contribution to journalArticlepeer-review

6 Scopus citations

Abstract

The DiMES materials probe exposed tungsten blocks with 0.3 and 1 mm high leading edges to DIII-D He plasmas in 2015 and 2016 viewed with high resolution IRTV. The 1-mm edge may have reached >3000 °C in a 3-s shot with a (parallel) heat load of ∼80 MW/m2 and ∼8.6 MW/m2 on the surface based on modeling. The experiments support ITER. Leading edges were also a concern in the DIII-D Metal Tile Experiment in 2016. Two toroidal arrays of divertor tiles had W-coated molybdenum inserts 50 mm wide radially. This paper presents data and thermal analyses.

Original languageEnglish
Pages (from-to)271-275
Number of pages5
JournalFusion Engineering and Design
Volume124
DOIs
StatePublished - Nov 2017

Keywords

  • DIII-D
  • High heat flux
  • Plasma facing component
  • Plasma surface interaction
  • Power handling
  • Tungsten

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