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Author(s):
N. Noda, V. Philipps and R. Neu
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Title:
A Review of Recent Experiments on W and High Z Materials as Plasma-Facing Components in Magnetic Fusion Devices
Date of publication:
Aug. 1996
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Key words:
high Z metals, molybdenum, tungsten, impurity accumulation, limiter, divertor, erosion, sputtering, redeposition, protecting layer, hydrogen retention, material development
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Abstract:
Since the 10th PSI conference in 1992, high Z refractory metals have been attracting growing interest as candidates for plasma facing materials, because of their resistance against erosion. In tokamaks such as TEXTOR, ASDEX-Upgrade, FTU, Alcator C-Mod, D III-D, considerable effort has been made to study the behavior of high Z impurity in the core and edge plasmas, erosion/redeposition processes at the limiter/divertor surfaces, hydrogen isotope retention, material development and tests etc. An interim review of these studies is given. Tentative conclusions are drawn in order to get a view and direction in the future studies.
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