Data for Erosion and Tritium Retention in Beryllium Plasma-Facing Materials

Beryllium is an attractive candidate for the "first wall" of a magnetic confinement nuclear fusion device because of its high conductivity, low activation and favourable properties as a plasma impurity.

This CRP enhanced the knowledge base on fundamental particle–material interaction processes involving beryllium in the fusion plasma environment, in particular physical and chemical sputtering by H, He and Be; the transport of hydrogen in beryllium; and the means to extract trapped tritium.