作者: Takumi Chikada , Hikari Fujita , Jan Engels , Anne Houben , Jumpei Mochizuki
DOI: 10.1016/J.JNUCMAT.2018.06.008
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摘要: Abstract Tritium permeation through structural materials is a critical issue in fusion reactors from the viewpoints of sufficient fuel balance and radiological hazard. Ceramic coatings have been investigated as tritium barrier for several decades; however, irradiation effects on are not elucidated. In this work, yttrium oxide were fabricated reduced activation ferritic/martensitic steels by radio frequency magnetron sputtering, their microstructures deuterium behaviors before after iron-ion at different temperatures. An as-deposited coating had columnar structure transformed into granular one annealing. amorphous layer formed near coating-substrate interface irradiated coatings, its thickness became thinner with increasing temperature. Voids approximately 20 nm diameter also coatings. Deuterium flux sample to 1 dpa room temperature was lowest among unirradiated samples, reduction factor indicated up 390. The disappeared measurements due damage recovery, while voids remained aggregated. would accelerate nucleation crystal, resulting decrease flux.