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- W2062458981 abstract "Low activation materials have to be developed toward fusion demonstration reactors. Ferritic steel, vanadium alloy and SiC/SiC composite are candidate materials of the first wall, vacuum vessel and blanket components, respectively. Although changes of mechanical-thermal properties owing to neutron irradiation have been investigated so far, there is little data for the plasma material interactions, such as fuel hydrogen retention and erosion. In the present study, deuterium retention and physical sputtering of low activation ferritic steel, F82H, were investigated by using deuterium ion irradiation apparatus." @default.
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- W2062458981 date "2005-04-01" @default.
- W2062458981 modified "2023-10-16" @default.
- W2062458981 title "Deuterium Retention and Physical Sputtering of Low Activation Ferritic Steel" @default.
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- W2062458981 doi "https://doi.org/10.1088/1009-0630/7/2/011" @default.
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