The implications of mixed-material plasma-facing surfaces in ITER
The implications of mixed-material plasma-facing surfaces in ITER
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DOI：
10.1016/j.jnucmat.2006.12.059
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发表时间：
2007-06
影响因子：
3.1
通讯作者：
R. Doerner
中科院分区：
文献类型：
--
作者：
R. Doerner
在所有等离子体约束装置中，从面向等离子体的表面侵蚀的材料将被输送并重新沉积在其他位置，有时是远程位置。如果器械中的面向等离子体的材料由不止一种元素组成，则面向等离子体的表面的成分很可能会随着时间的推移而演变，并且可能表现出与最初安装的材料大不相同的等离子体相互作用特性。这些等离子体产生的材料，或混合材料，是本审查文件的主题，重点是ITER相关的混合材料，即碳，钨和铍。知识有关的形成条件，侵蚀行为和氢同位素保留性能的每一个二元组合的材料进行了说明。讨论了有关材料的第三组合的可用信息。
In all plasma-confinement devices, material eroded from plasma-facing surfaces will be transported and redeposited at other, sometimes remote, locations. If the plasma-facing material in a device consists of more than a single element there is a high probability that the composition of the plasma-facing surfaces will evolve over time and may exhibit plasma-interaction properties much different from the originally installed material. These plasma-created materials, or mixed materials, are the subjects of this review paper which focuses on the ITER relevant mix of materials, namely carbon, tungsten and beryllium. Knowledge concerning the formation conditions, erosion behavior and hydrogen isotope retention properties of each binary combination of materials is described. Where available information concerning tertiary combinations of materials is discussed.