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 favorable 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.

Andreas KIRSCHNER Forschungszentrum Jülich (FZJ)
Andreas MAURACHER Institute for Ion Physics and Applied Physics, Universität Innsbruck
Arkadi KRETER Forschungszentrum Jülich (FZJ)
Carolina BJÖRKAS Department of Physics, University of Helsinki
Christian LINSMEIER Forschungszentrum Jülich (FZJ)
Daisuke NISHIJIMA Center for Energy Research, UCSD
Dmitry BORODIN Forschungszentrum Jülich (FZJ)
Hyun-Kyung CHUNG National Fusion Research Institute (NFRI)
Michael PROBST Institute for Ion Physics and Applied Physics, Universität Innsbruck
NAKAMURA Hiroki Center for Computational Science and E-Systems (CCSE), Japan Atomic Energy Agency (JAEA)
Sebastiján BREZINSEK Forschungszentrum Jülich (FZJ)
Stephan IRLE Oak Ridge National Laboratory (ORNL)