Tritium permeation through structural materials in fusion reactor blanket systems is a critical issue from the viewpoints of fuel loss and radiological safety. Ceramic coatings have been investigated to prevent tritium permeation; however, corrosion of the coatings by blanket materials, especially corrosive liquid tritium breeders such as lithium-lead is serious. In our previous study, the improvement of permeation reduction performance using an erbium oxide (ErO)-zirconium oxide (ZrO) two-layer coating was confirmed, but it did not show substantial corrosion resistance. In this study, various multi-layer coatings were fabricated by metal organic decomposition and then exposed to lithium-lead under static conditions to investigate precise corrosion behaviors of multi-layer coatings. After lithium-lead exposure for 1000 h at 600 °C, the outermost ErO layer almost disappeared, while the outermost ZrO layer remained, indicating that ZrO is more suitable as the outermost layer. However, many cracks and peelings were observed on the outermost ZrO layer in the cases of the samples having four coating interfaces. The optimization of layer combination and the control of adhesion between the coatings are required to reduce the degradation of multi-layer coatings.

中文翻译：

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多层陶瓷涂层在液态锂铅中的腐蚀试验

从燃料损失和辐射安全的角度来看，氚通过聚变反应堆包层系统中的结构材料的渗透是一个关键问题。陶瓷涂层已被研究用于防止氚渗透；然而，覆盖层材料，特别是腐蚀性液体氚增殖剂（例如锂铅）对涂层的腐蚀是严重的。在我们之前的研究中，证实了使用氧化铒（ErO）-氧化锆（ZrO）两层涂层可以提高渗透减少性能，但它并没有表现出实质性的耐腐蚀性。在这项研究中，通过金属有机分解制备了各种多层涂层，然后在静态条件下暴露于锂铅中，以研究多层涂层的精确腐蚀行为。锂铅在600℃下暴露1000h后，最外层的ErO层几乎消失，而最外层的ZrO层仍然存在，表明ZrO更适合作为最外层。然而，在具有四个涂层界面的样品的情况下，在最外层ZrO层上观察到许多裂纹和剥落。需要优化层组合和控制涂层之间的附着力来减少多层涂层的降解。