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 permeation barrier for several decades; however, irradiation effects of the coatings on permeation are not elucidated. In this work, yttrium oxide coatings were fabricated on reduced activation ferritic/martensitic steels by radio frequency magnetron sputtering, and their microstructures and deuterium permeation behaviors were investigated before and after iron-ion irradiation at different temperatures. An as-deposited coating had a columnar structure and transformed into a granular one after annealing. An amorphous layer formed near the coating-substrate interface of irradiated coatings, and its thickness became thinner with increasing irradiation temperature. Voids of approximately 20 nm in diameter also formed in the irradiated coatings. Deuterium permeation flux of the sample irradiated to 1 dpa at room temperature was the lowest among the unirradiated and irradiated samples, and a permeation reduction factor indicated up to 390. The amorphous layer disappeared after deuterium permeation measurements due to damage recovery, while the voids remained and aggregated. The irradiation damage would accelerate nucleation of the crystal, resulting in a decrease of the permeation flux.

从足够的燃料平衡和放射危害的角度来看，through通过结构材料的渗透是聚变反应堆中的关键问题。数十年来，陶瓷涂层已被用作ium渗透屏障。然而，没有阐明涂层对渗透的辐射作用。在这项工作中，通过射频磁控溅射在还原活化的铁素体/马氏体钢上制备了氧化钇涂层，并研究了在不同温度下铁离子辐照前后的微观结构和氘的渗透行为。沉积后的涂层具有柱状结构，并且在退火后转变成颗粒状。在辐照涂层的涂层-基材界面附近形成的非晶层，随着照射温度的升高，其厚度变薄。在被辐照的涂层中也形成了直径约20nm的空隙。室温下辐照至1 dpa的样品中氘的渗透通量在未辐照和辐照的样品中最低，渗透减少系数高达390。由于损伤恢复，氘渗透后非晶层消失了，而空隙仍然存在并汇总。辐照损伤会加速晶体的成核作用，导致渗透通量降低。渗透减少系数高达390。由于氘的损伤恢复，非晶态层在氘的渗透测量后消失了，而空隙却保留并聚集了。辐照损伤会加速晶体的成核作用，导致渗透通量降低。渗透减少系数高达390。由于氘的损伤恢复，非晶态层在氘的渗透测量后消失了，而空隙却保留并聚集了。辐照损伤会加速晶体的成核作用，导致渗透通量降低。