volume 41, issue 9, P1243-1252 2001
DOI: 10.1088/0029-5515/41/9/313
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Abstract: The DIII-D tokamak has demonstrated an operational scenario where the graphite-covered divertor is free of net erosion. Reduction of divertor carbon erosion is accomplished using a low temperature (detached) divertor plasma that eliminates physical sputtering. Likewise, the carbon source rate arising from chemical erosion is found to be very low in the detached divertor. Near strikepoint regions, the rate of carbon deposition is 3 cm/burn-year, with a corresponding hydrogenic codeposition rate > 1 kg/m 2 /burn…

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