SiC exhibits a remarkable resistance to neutron irradiation damage and, being a low-Z material, is seen as a potential material candidate for plasma-facing components in magnetic confinement fusion reactors. The current work investigates the reclamation of deuterium from C-Si codeposits produced by sputter-deposition at temperatures from 300 K to 700 K using thermo-oxidation at 350 °C and 400 °C (623 or 673 K). While initial D content was found to be close to that of similarly-produced pure carbon codeposits, hydrogen removal from the investigated C-Si codeposits was significantly reduced comparatively. This reduced removal behaviour was found to follow closely with that observed for B-C codeposits from the DIII-D tokamak. This suggests that hydrogen removal via thermo-oxidation, where a non-carbon inclusion is known to form a stable oxide, is unlikely to be effective.

中文翻译：

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使用热氧化从 C-Si 共沉积物中回收氘

SiC 具有出色的抗中子辐照损伤能力，并且作为一种低 Z 材料，被视为磁约束聚变反应堆中面向等离子体的组件的潜在候选材料。目前的工作研究了利用 350 °C 和 400 °C（623 或 673 K）下的热氧化，从 300 K 至 700 K 温度下溅射沉积产生的 C-Si 共沉积物中回收氘。虽然发现初始 D 含量接近于类似生产的纯碳共沉积物的含量，但从所研究的 C-Si 共沉积物中去除的氢相对显着减少。人们发现这种减少的去除行为与 DIII-D 托卡马克中观察到的 BC 共沉积行为密切相关。这表明通过热氧化去除氢不太可能有效，其中已知非碳夹杂物会形成稳定的氧化物。