Abstract
The movable limiter for the Tokamak Fusion Test Reactor (TFTR) is composed of an Inconel X-750 backing plate covered with titanium carbide coated graphite tiles. It has been used for ohmic heating discharges at input powers up to about 2 MW for durations up to 3 s. Even though these levels were well within the design requirements, discharges showed high levels (up to 1%) of titanium contamination. It was observed that certain tiles were showing substantial coating removal which became progressively worse as more discharges were made. After about 800 discharges the tiles were removed. A few of the tiles were examined in the Sandia external beam facility. This analysis showed that the TiC coating was completely removed over large areas. There was also evidence of plasma deposited material on the tiles. The thickness of the remaining coating from this beam analysis agreed with the thickness determined from sectioning control coupons from the production runs. There was a weak correlation between damage and coating thickness. The correlation was such that there was a higher probability of coating failure as the coating thickness increased from 15 μm to 40 μm. Test were done using the ASTM-C-633 procedure for measuring coating bond strength. The adhesion strength agreed well with the behavior observed in TFTR. The coating has been removed, and the tiles reinstalled.
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