Divertor Materials Evaluation System (DiMES)

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The mission of the Divertor Materials Evaluation System (DiMES) in DIII-D is to establish an integrated data base from measurements in the divertor of a tokamak in order to address some of the ITER and fusion power reactor plasma material interaction issues. Carbon and metal coatings of Be, W, V, and Mo were exposed to the steady-state outer strike point on DIII-D for 4-18 s. These short exposure times ensure controlled exposure conditions, and the extensive arrays of DIII-D divertor diagnostics provide a well-characterized plasma for modeling efforts. Postexposure analysis provides a direct measure of surface material erosion rates and ... continued below

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18 p.

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Wong, C. P.; West, W. P.; Whyte, D. G.; Bastasz, R. J.; Brooks, J. & Wampler, W. R. November 1997.

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Description

The mission of the Divertor Materials Evaluation System (DiMES) in DIII-D is to establish an integrated data base from measurements in the divertor of a tokamak in order to address some of the ITER and fusion power reactor plasma material interaction issues. Carbon and metal coatings of Be, W, V, and Mo were exposed to the steady-state outer strike point on DIII-D for 4-18 s. These short exposure times ensure controlled exposure conditions, and the extensive arrays of DIII-D divertor diagnostics provide a well-characterized plasma for modeling efforts. Postexposure analysis provides a direct measure of surface material erosion rates and the amount of retained deuterium. For carbon, these results match closely with the results of accumulated carbon deposition and erosion, and the corresponding deuterium retention of long term exposure tiles in DIII-D. Deuterium retention of different materials was measured using the {sup 3}He(d,p) {sup 4}He nuclear reaction. For carbon, these measurements showed peak deuterium areal density of about 8 {times} 10 {sup 18} D/cm{sup 2} in a co-deposited layer about 6 {micro}m deep, mainly at the usually detached inboard divertor leg. That layer of carbon near the inner divertor strike point has an atomic saturation concentration of D/C {approx} 0.25, which is not significantly lower than the laboratory-measured saturation retention of 0.4. Under the carbon contaminated background plasma of DIII-D, metal coatings of Be, V, Mo, and W were exposed to the steady state outer strike point under ELMing and ELM-free H-mode discharges. The rate of material erosion and tritium retention were measured. As expected, W shows the lowest erosion rate at 0.1 nm/s and the lowest deuterium uptake.

Physical Description

18 p.

Notes

INIS; OSTI as DE98002634

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  • 8. international conference on fusion reactor materials (ICFRM), Sendai (Japan), 26-31 Oct 1997

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  • Other: DE98002634
  • Report No.: GA--A22743
  • Report No.: CONF-971090--
  • Grant Number: AC03-89ER52153;AC04-94AL85000;W-31109-ENG-38;FG03-95ER54294
  • Office of Scientific & Technical Information Report Number: 642774
  • Archival Resource Key: ark:/67531/metadc695602

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  • November 1997

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  • Aug. 14, 2015, 8:43 a.m.

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  • Aug. 1, 2016, 6:34 p.m.

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Wong, C. P.; West, W. P.; Whyte, D. G.; Bastasz, R. J.; Brooks, J. & Wampler, W. R. Divertor Materials Evaluation System (DiMES), article, November 1997; San Diego, California. (digital.library.unt.edu/ark:/67531/metadc695602/: accessed August 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.