Test results for a C+SiC alloy coating on limiter/armor tiles in Doublet III
Conference
·
OSTI ID:5264543
A new carbon plus silicon carbide (C+SiC) alloy material has been developed for use on in-vessel components of plasma devices. This material is nominally 10 wt. % SiC and is applied as a coating to graphite substrates. It has been tested in the limiter/beam armor position of Doublet III for over 11,000 plasma shots. The performance is excellent and the material is highly resistant to thermal shocks, thermal cycling, and erosion from plasma boundary and neutral beam interactions. This promises a long useful life for components in fusion vesels.
- Research Organization:
- GA Technologies, Inc., San Diego, CA (USA)
- DOE Contract Number:
- AT03-76ET51011
- OSTI ID:
- 5264543
- Report Number(s):
- GA-A-17350; CONF-831203-101; ON: DE84005842
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
CARBIDES
CARBON
CARBON COMPOUNDS
COATINGS
DOUBLET REACTORS
ELEMENTAL MINERALS
ELEMENTS
EROSION
GRAPHITE
LIMITERS
MATERIALS TESTING
MINERALS
NONMETALS
PERFORMANCE TESTING
SHIELDING
SILICON CARBIDES
SILICON COMPOUNDS
SUBSTRATES
TESTING
THERMAL CYCLING
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
CARBIDES
CARBON
CARBON COMPOUNDS
COATINGS
DOUBLET REACTORS
ELEMENTAL MINERALS
ELEMENTS
EROSION
GRAPHITE
LIMITERS
MATERIALS TESTING
MINERALS
NONMETALS
PERFORMANCE TESTING
SHIELDING
SILICON CARBIDES
SILICON COMPOUNDS
SUBSTRATES
TESTING
THERMAL CYCLING
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS