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  Short and long range transport of materials eroded from wall components in fusion devices

Wienhold, P., Philipps, V., Kirschner, A., Huber, A., von Seggern, J., Esser, H. G., et al. (2003). Short and long range transport of materials eroded from wall components in fusion devices. Journal of Nuclear Materials, 313-316, 311-320. doi:10.1016/S0022-3115(02)01347-8.

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 Creators:
Wienhold, P.1, Author           
Philipps, V.2, Author
Kirschner, A.2, Author
Huber, A.2, Author
von Seggern, J.2, Author
Esser, H. G.2, Author
Hildebrandt, D.1, Author           
Mayer, M.3, Author           
Rubel, M.2, Author
Schneider, W.4, Author           
Affiliations:
1Plasma Diagnostics Group (HUB), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856324              
2Institute of Plasma Physics, Research Centre Jülich, Forschungszentrum Jülich GmbH, Ass. EURATOM-KFA, Trilateral Euregio Cluster, P.O. Box 1913, D-52425, Jülich, Germany; Royal Institute of Technology, Alfvén Laboratory, Ass. EURATOM-VR, S-10044, Stockholm, Sweden, ou_persistent22              
3Material Research (MF), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856328              
4Tokamak Theory (TOK), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856309              

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Free keywords: 15th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 15), Gifu, 2002-05-26 to 2002-05-31
 Abstract: Carbon sources and the sinks have been quantified in TEXTOR and are discussed in terms of short and long range transport. The major source (22 g/h) is the graphite belt limiter, but part (10 g/h) of the carbon is directly re-deposited after short range transport. Long range transport causes flake formation on obstacles and neutralisers, but little and deuterium rich (D/C≈0.7) deposition in remote areas. The rest is leaving via the pumps in gaseous form. This behaviour is different from that in JET where large amounts of deuterium rich deposits were found in the louvers. Tungsten is favoured for the ITER divertors because of its low sputtering yield for hydrogen, but melting and erosion by carbon may be an additional concern. The short range transport of tungsten has been investigated in a well defined experiment and quantitatively re-constructed by means of the ERO-TEXTOR code. Code validation is necessary in order to increase the confidence and the applicability to JET and ITER.

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Language(s): eng - English
 Dates: 2003
 Publication Status: Issued
 Pages: -
 Publishing info: -
 Table of Contents: -
 Rev. Type: Peer
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Title: Journal of Nuclear Materials
  Alternative Title : J. Nucl. Mater.
Source Genre: Journal
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Publ. Info: Copyright © 2003 Elsevier Science B.V. All rights reserved
Pages: - Volume / Issue: 313-316 Sequence Number: - Start / End Page: 311 - 320 Identifier: -