Suppression of erosion in the DIII-D divertor with detached plasmas

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The ability to withstand disruptions makes carbon-based materials attractive for use as plasma-facing components in divertors. However, such materials suffer high erosion rates during attached plasma operation which, in high power long pulse machines, would give short component lifetimes and high tritium inventories. The authors present results from recent experiments in DIII-D, in which the Divertor Materials Evaluation System (DiMES) was used to examine erosion and deposition during short exposures to well defined plasma conditions. These studies show that during operation with detached plasmas, produced by gas injection, net erosion is suppressed everywhere in the divertor. Net deposition of carbon ... continued below

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16 p.

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Wampler, William R.; Bastasz, Robert J.; Whyte, D. G.; Wong, C. P. C. & West, W. P. May 25, 2000.

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  • Sandia National Laboratories
    Publisher Info: Sandia National Labs., Albuquerque, NM, and Livermore, CA (United States)
    Place of Publication: Albuquerque, New Mexico

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Description

The ability to withstand disruptions makes carbon-based materials attractive for use as plasma-facing components in divertors. However, such materials suffer high erosion rates during attached plasma operation which, in high power long pulse machines, would give short component lifetimes and high tritium inventories. The authors present results from recent experiments in DIII-D, in which the Divertor Materials Evaluation System (DiMES) was used to examine erosion and deposition during short exposures to well defined plasma conditions. These studies show that during operation with detached plasmas, produced by gas injection, net erosion is suppressed everywhere in the divertor. Net deposition of carbon with deuterium was observed at the inner and outer strikepoints and in the private-flux region between strikepoints. For these low temperature plasmas (T{sub e} < 2eV), physical sputtering is eliminated. These results show that with detached plasmas, the location of carbon net erosion and the carbon impurity source, probably lies outside the divertor. Physical or chemical sputtering by charge-exchange neutrals or ions in the main plasma chamber is a probable source of carbon under these plasma conditions.

Physical Description

16 p.

Notes

INIS; OSTI as DE00756167

Medium: P; Size: 16 pages

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  • 14th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, Rosenheim (DE), 05/22/2000--05/27/2000

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  • Report No.: SAND2000-1327C
  • Grant Number: AC04-94AL85000
  • Office of Scientific & Technical Information Report Number: 756167
  • Archival Resource Key: ark:/67531/metadc710148

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Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • May 25, 2000

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • April 7, 2017, 3:20 p.m.

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Wampler, William R.; Bastasz, Robert J.; Whyte, D. G.; Wong, C. P. C. & West, W. P. Suppression of erosion in the DIII-D divertor with detached plasmas, article, May 25, 2000; Albuquerque, New Mexico. (digital.library.unt.edu/ark:/67531/metadc710148/: accessed September 25, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.