AI 中文总结
通过DIII-D的公私部门实验，对44种先进面向等离子体材料进行比较评估，涵盖多种条件下的暴露测试，得出不同材料性能数据，为聚变试验工厂材料筛选及相关材料开发提供跨材料基准。
AI 中文摘要
一项在DIII-D上的协同活动对来自12个机构（包括四个公私融合伙伴关系）的44种先进面向等离子体材料进行了暴露和比较评估，以支持聚变试验工厂壁和偏滤器材料的向下选择。使用偏滤器材料评估系统（DiMES）在欧姆、L模和H模条件下，以及在边缘局域模下，在0.2 - 2.5MW m⁻²的平面几何形状和10 - 15MW m⁻²的10°角几何形状下对样品进行暴露。工程钨结构保持完整；长纤维Wf/W表现出最明显的裂纹阻止行为。W-Re和K掺杂的W表现出接近ITER-W的响应，而增材制造的W-Ta对热通量敏感，平面样品质量损失0.64mg，角形样品质量损失2.19 - 2.87mg。在550°C下辐照至0.3dpa后，中子辐照的ITER级W保留的氘比原始W多2.8倍，而TiB₂在欧姆组中显示出最低的D₂释放。VTaHfMo是最稳定的难熔多主元合金。NbC和（Nb₀.₅Ta₀.₅）C质量损失0.02 - 0.03mg保持完整，而ZrC损失7mg。CVD SiC保持宏观完整性，但有效Si侵蚀产率为0.5，比之前DIII-D的趋势高约5 - 10倍。可再生硼卵石棒经历了可控的衰退；13%释放的硼在外部打击点附近被电离，高达50%在局部被回收。初始原位铬总侵蚀测量值为10⁻²量级。这些结果共同为聚变试验工厂的向下选择和未来人工智能/机器学习辅助的面向等离子体材料开发提供了跨材料基准。
英文摘要
A coordinated DIII-D campaign exposed and comparatively assessed 44 advanced plasma-facing materials from 12 institutions, including four public-private fusion partnerships, to support fusion pilot plant wall and divertor material down-selection. Samples were exposed using the Divertor Materials Evaluation System (DiMES) under Ohmic, L-mode, and H-mode conditions with edge-localized modes, at 0.2-2.5 MW m$^{-2}$ on flush geometries and 10-15 MW m$^{-2}$ on 10$^{\circ}$ angled geometries. Engineered tungsten architectures retained integrity; long-fiber Wf/W showed the clearest crack-arrest behavior. W-Re and K-doped W showed near-ITER-W-like responses, while additively manufactured W-Ta showed heat-flux-sensitive mass losses of 0.64 mg for the flat sample and 2.19-2.87 mg for angled samples. After irradiation to 0.3 dpa at 550$^{\circ}$C, neutron-irradiated ITER-grade W retained 2.8 times more deuterium than pristine W, while TiB$_2$ showed the lowest D$_2$ release in the Ohmic set. VTaHfMo was the most stable refractory multi-principal-element alloy. NbC and (Nb$_{0.5}$Ta$_{0.5}$)C retained integrity with 0.02-0.03 mg mass loss, whereas ZrC lost 7 mg. CVD SiC retained macroscopic integrity but exhibited an effective Si erosion yield of 0.5, about 5-10 times above prior DIII-D trends. Renewable boron pebble rods underwent controlled recession; 13% of released boron was ionized near the outer strike point and up to 50% was recovered locally. Initial in-situ chromium gross-erosion measurements yielded values of order $10^{-2}$. Together, these results provide cross-material benchmarks for fusion pilot plant down-selection and future AI/ML-assisted plasma-facing-material development.
Comments20 pages, 16 figures, 3 tables
