Initial testing of coated limiters in ISX-B
Conference
·
OSTI ID:5478148
Low-Z coatings on graphite substrates have been developed for testing as limiters in the Impurity Study Experiment (ISX-B) tokamak. Laboratory and tokamak testings have been accomplished. The laboratory tests included thermal shock experiments by means of pulsed e-beam irradiation, arcing experiments, and hydrogen and xenon ion erosion experiments. The tokamak testing consisted of ohmically heated plasma exposures with energy depositions up to 10 kJ/discharge on the limiters. The coatings, applied by chemical vapor deposition, consisted of TiB/sub 2/ and TiC deposited on POCO graphite substrates.
- Research Organization:
- Oak Ridge National Lab., TN (USA); Sandia Labs., Albuquerque, NM (USA)
- Sponsoring Organization:
- USDOE Office of Fusion Energy
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5478148
- Report Number(s):
- CONF-800455--8
- 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
BORIDES
BORON COMPOUNDS
CARBIDES
CARBON
CARBON COMPOUNDS
COATINGS
CURRENTS
ELECTRIC ARCS
ELECTRIC CURRENTS
ELECTRIC DISCHARGES
ELEMENTS
GRAPHITE
ISX TOKAMAK
LIMITERS
NONMETALS
PERFORMANCE TESTING
SUBSTRATES
TESTING
THERMAL CYCLING
THERMONUCLEAR REACTORS
TITANIUM BORIDES
TITANIUM CARBIDES
TITANIUM COMPOUNDS
TOKAMAK TYPE REACTORS
TRANSITION ELEMENT COMPOUNDS
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
BORIDES
BORON COMPOUNDS
CARBIDES
CARBON
CARBON COMPOUNDS
COATINGS
CURRENTS
ELECTRIC ARCS
ELECTRIC CURRENTS
ELECTRIC DISCHARGES
ELEMENTS
GRAPHITE
ISX TOKAMAK
LIMITERS
NONMETALS
PERFORMANCE TESTING
SUBSTRATES
TESTING
THERMAL CYCLING
THERMONUCLEAR REACTORS
TITANIUM BORIDES
TITANIUM CARBIDES
TITANIUM COMPOUNDS
TOKAMAK TYPE REACTORS
TRANSITION ELEMENT COMPOUNDS