作者: B. Baretzky , W. Eckstein , R.P. Schorn
DOI: 10.1016/0022-3115(95)00040-2
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摘要: Abstract High-Z alloys containing a small portion of lithium have been studied in recent years with emphasis on their behavior nuclear fusion relevant reactor environments. Surface segregation and diffusion the component may open chance to produce material for first wall components reactors, which shows self-replenishing feature concerning low-Z coating high-Z substrate, being highly desired issue physics plasma-wall interaction. This article will review status experimental computational results Cu/Li furthermore give an extrapolation plasma environment expected next generation. Mandatory improvements that are still necessary application Li-containing future machines discussed.