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Thermal management of tungsten leading edges in DIII-D...

Publication Type
Conference Paper
Journal Name
Fusion Engineering and Design
Publication Date
Page Numbers
271 to 275
Volume
124
Issue
1
Conference Name
29th Symposium on Fusion Technology (SOFT)
Conference Location
Prague, Czech Republic
Conference Sponsor
the Ministry of Education, Youth and Sports in Czech Republic
Conference Date
-

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.