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High-Z alloys containing a small portion of lithium have been studied in recent years with emphasis on their behaviour in nuclear fusion relevant reactor environments. Surface segregation and diffusion of the lithium component may produce a material for first wall components in fusion reactors, which shows a self-replenishing feature containing a low-Z coating on a high-Z substrate. This article reviews the status of experimental and computational results concerning Cu/Li, and extrapolates from these results to the plasma environment expected for a fusion reactor of the next generation. Material improvements that are necessary for application of Li-containing alloys in future machines are discussed.

Additional information

Authors: BARETZKY B, Forschungszentrum Jülich GmbH (KFA) (DE);SCHORN R P, Forschungszentrum Jülich GmbH (KFA) (DE);ECKSTEIN W, Max-Planck-Institut für Plasmaphysik, Garching bei München (DE)
Bibliographic Reference: Article: Journal of Nuclear Materials, Vol. 224 (1995) pp. 50-70
Record Number: 199510882 / Last updated on: 1995-08-03
Original language: en
Available languages: en
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