Performance testing of carbon–carbon composites as plasma-facing materials for magnetic fusion reactors

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Abstract
This paper describes the results of a study of the properties affecting the performance of carbon–carbon composites as plasma-facing materials in magnetic fusion reactors. A composite has already been chosen for the protective limiter of the rf antenna in the Tokamak Fusion Test Reactor and composites are being considered for divertor applications in the Compact Ignition Tokamak. In direct comparison with results for POCO AXF-5Q graphite, the composites were able to survive more severe high heat flux conditions, released less water vapor and gases during the thermal outgassing tests, and retained less tritium during exposure to tritium gas and plasma.

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