Thermal management of tungsten leading edges in DIII-D

Journal Article · Sat Apr 29 00:00:00 EDT 2017 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2017.04.060· OSTI ID:1373578

Nygren, Richard E. ^[1]; Rudakov, Dmitry L. ^[2]; Murphy, Christopher ^[3]; Watkins, Jonathan D. ^[1]; Unterberg, Ezekial A. ^[4]; Barton, Joseph L. ^[1]; Stangeby, Peter C. ^[5]

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1. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
2. Univ. of California, San Diego, La Jolla, CA (United States)
3. General Atomics, San Diego, CA (United States)
4. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
5. Univ. of Toronto Institute for Aerospace Studies, Toronto (Canada)

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 >2400° C in a 3-s shot with a (parallel) heat load of ~50 MW/m² and ~10 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 rings of divertor tiles had W-coated molybdenum inserts 50 mm wide radially. This study presents data and thermal analyses.

• Research Organization: General Atomics, San Diego, CA (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: FC02-04ER54698
• OSTI ID: 1373578
• Journal Information: Fusion Engineering and Design, Vol. 124; ISSN 0920-3796
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Plasma facing component
Tungsten
High heat flux
DIII-D
Power handling
Plasma surface interaction