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.; Hildebrandt, D.; Mayer, M.; Rubel, M.; Schneider, W.

doi:10.1016/S0022-3115(02)01347-8

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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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Datensatz-Permalink: https://hdl.handle.net/11858/00-001M-0000-0027-2F3E-8 Versions-Permalink: https://hdl.handle.net/11858/00-001M-0000-0029-0325-2

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Urheber:
Wienhold, P.¹, Autor
Philipps, V.², Autor
Kirschner, A.², Autor
Huber, A.², Autor
von Seggern, J.², Autor
Esser, H. G.², Autor
Hildebrandt, D.¹, Autor
Mayer, M.³, Autor
Rubel, M.², Autor
Schneider, W.⁴, Autor

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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Schlagwörter: 15th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI 15), Gifu, 2002-05-26 to 2002-05-31

Zusammenfassung: 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.