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001     57840
005     20240709094304.0
024 7 _ |2 DOI
|a 10.1016/j.fusengdes.2005.07.037
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041 _ _ |a eng
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|a Nuclear Science & Technology
100 1 _ |a Rubel, M. J.
|b 0
|0 P:(DE-HGF)0
245 _ _ |a Overview of comprehensive characterisation of erosion zones on plasma facing components
260 _ _ |a New York, NY [u.a.]
|b Elsevier
|c 2006
300 _ _ |a
336 7 _ |a Journal Article
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336 7 _ |a article
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440 _ 0 |a Fusion Engineering and Design
|x 0920-3796
|0 2169
|y 1
|v 81
500 _ _ |a Record converted from VDB: 12.11.2012
520 _ _ |a Morphology of carbon plasma facing components retrieved from the TEXTOR tokamak after long operation periods and exposure to total particle doses exceeding 7 x 10(26) m(-2) was determined. Emphasis was on the composition and structure of the erosion zones. Tiles from two limiters-the main toroidal belt pump ALT-II and auxiliary inner bumper-were examined using high-resolution microscopy, surface profilometry, ion beam analysis techniques and energy dispersive X-ray spectroscopy. The essence of results regarding the net-erosion zones is following: (i) microstructure of surfaces is significantly smoother than on a non-exposed graphite, whereas carbon fibre composites show similar appearance prior to the exposure and after; (ii) deuterium retention is 2-5 x 10(21) m(-2); (iii) the presence of plasma impurity atoms (e.g. metals) is detected predominantly in small cavities acting as local shadowed areas on the surface. The results are discussed in terms of processes of material erosion/re-deposition and tokamak operation conditions influencing the morphology of wall components. (c) 2005 Elsevier B.V. All rights reserved.
536 _ _ |a Rationelle Energieumwandlung
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653 2 0 |2 Author
|a graphite
653 2 0 |2 Author
|a erosion
653 2 0 |2 Author
|a plasma facing components
653 2 0 |2 Author
|a fuel inventory
653 2 0 |2 Author
|a TEXTOR
700 1 _ |a Fortuna, E.
|b 1
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700 1 _ |a Kreter, A.
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700 1 _ |a Wessel, E.
|b 3
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700 1 _ |a Philipps, V.
|b 4
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700 1 _ |a Kurzydlowski, K. J.
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773 _ _ |a 10.1016/j.fusengdes.2005.07.037
|g Vol. 81
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|t Fusion engineering and design
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|x 0920-3796
856 7 _ |u http://dx.doi.org/10.1016/j.fusengdes.2005.07.037
909 C O |o oai:juser.fz-juelich.de:57840
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|a JCR/ISI refereed
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|l Institut für Plasmaphysik
|d 31.12.2006
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|l Werkstoffstruktur und Eigenschaften
|d 31.12.2006
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