Erosion results from DiMES and design implications to ITER and Starlite

Journal Article · Mon Dec 30 23:00:00 EST 1996 · Fusion Technology

OSTI ID:447397

Wong, C P.C.; West, W P ^[1]; Whyte, D G ^[2]; Bastaz, R J ^[3]; Wampler, W R ^[4]

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1. General Atomics, San Diego, CA (United States)
2. INRS, Varennes, Quebec (Canada)
3. Sandia National Lab., Livermore, CA (United States)
4. Sandia National Lab., Albuquerque, NM (United States)

Using the DiMES mechanism at DIII-D, erosion rates of graphite, and metallic coatings of Be, V, Mo, and W have been measured under different plasma operating conditions. The measured net erosion rate for C is substantial (16 nm/s) during ELMing H-mode at a heat flux of 2 MW/m{sup 2}. Measured gross erosion rates of the metals are lower than expected from sputtering yields, most likely due to heavy surface contamination by carbon. The measured erosion of W is substantially lower than the other materials, and when account is taken for redeposition, it is shown to be a viable candidate for the Starlite reactor`s divertor. 15 refs., 1 fig., 1 tab.

• DOE Contract Number: AC03-89ER51114; AC04-94AL85000; W-31109-ENG-38
• OSTI ID: 447397
• Report Number(s): CONF-9606116--
• Journal Information: Fusion Technology, Journal Name: Fusion Technology Journal Issue: 3 Vol. 30; ISSN 0748-1896; ISSN FUSTE8
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BERYLLIUM
CARBON
CONTAMINATION
DESIGN
DIVERTORS
EROSION
GRAPHITE
ITER TOKAMAK
MOLYBDENUM
NUMERICAL DATA
PLASMA DIAGNOSTICS
PLASMA IMPURITIES
PROTECTIVE COATINGS
TUNGSTEN
VANADIUM