Erosion results from DiMES and design implications to ITER and Starlite

Conference · Mon Jul 01 00:00:00 EDT 1996

OSTI ID:434992

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

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1. General Atomics, San Diego, CA (United States)
2. Sandia National Labs., Livermore, CA (United States)
3. INRS, Varennes, PQ (Canada). Energie et Materiaux
4. Sandia National Labs., 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.

• Research Organization: General Atomics, San Diego, CA (United States); Sandia National Labs., Livermore, CA (United States); Sandia National Labs., Albuquerque, NM (United States); Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE Office of Energy Research, Washington, DC (United States)
• DOE Contract Number: AC03-89ER51114; AC04-94AL85000; W-31109-ENG-38
• OSTI ID: 434992
• Report Number(s): GA-A--22392; CONF-9606116--89; ON: DE97001151
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BERYLLIUM
COATINGS
DIVERTORS
DOUBLET-3 DEVICE
EDGE LOCALIZED MODES
EROSION
GRAPHITE
H-MODE PLASMA CONFINEMENT
ITER TOKAMAK
MOLYBDENUM
PLASMA
THERMONUCLEAR REACTOR MATERIALS
TUNGSTEN
VANADIUM