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- W2057245470 abstract "Tungsten is a promising candidate for plasma-facing materials in fusion reactors. In this work, two types of W materials were investigated: (i) sintered and forged tungsten (ITER-grade Japan, grain sizes 2–100 μm, elongated normal to the surface) and (ii) the same W grade, but after additional re-crystallization (at 2073 K, grain size ∼50 μm). The samples were exposed to deuterium with an ion energy of 38 eV D−1, a fluence of 1027 D m−2 and a flux of ∼1022 D m−2 s−1 in a plasma generator at elevated temperatures (320–700 K). The D retention (determined by thermal desorption spectroscopy and nuclear reaction analysis) of both sample types is compared. The samples were analysed with scanning electron microscopy combined with a focused ion beam for iterative cross-sectioning to obtain three-dimensional (3D) data of the sub-surface. Electron backscattered diffraction was applied to determine the grain orientation and deformation. First nano-secondary ion mass spectroscopy investigations were performed on a D-loaded sample to analyse the lateral accumulation of H/D on the surface." @default.
- W2057245470 created "2016-06-24" @default.
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- W2057245470 date "2011-12-01" @default.
- W2057245470 modified "2023-10-03" @default.
- W2057245470 title "Sub-surface structures of ITER-grade W (Japan) and re-crystallized W after ITER-similar low-energy and high-flux D plasma loadings" @default.
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- W2057245470 doi "https://doi.org/10.1088/0031-8949/2011/t145/014039" @default.
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