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Plasma-facing materials for fusion devices

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Abstract

In a future D/T fusion reactor the walls of the vessel containing the magnetically confined hot plasma have to stand simultaneously very high power, particle and neutron loads. In today’s high temperature plasma experiments at the areas of the highest load, i.e. the divertor and the limiters, W, Mo and Carbon (CFC) are used and Be, W, Mo, Inconel and stainless steel are at the other wall areas. These materials are also envisaged for future bigger fusion experiments, such as ITER [1–3]. The resistance of these materials to the different expected higher loads in a fusion reactor is only partly known and more investigations are needed with respect to find better materials and/or a modification of the divertor.

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  1. Max Planck-Institut für Plasmaphysik, EURATOM Association, Garching, Germany

    Rainer Behrisch

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Behrisch, R. Plasma-facing materials for fusion devices. J. Surf. Investig. 4, 549–562 (2010). https://doi.org/10.1134/S1027451010040014

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