Plasma-wall Interaction with Reduced-activation Steel Surfaces in Fusion Devices

Various kinds of reduced-activation steel are being considered as wall material for a fusion reactor, such as the planned DEMO demonstration power plant. However, not enough is known about plasma interaction, erosion and tritium retention in such steels.

This CRP will enhance the knowledge base and develop new databases on the interaction of fusion plasma with the reduced-activation steel alloys that are being considered for constructing the plasma-facing components of a fusion reactor. It will seek to quantify the erosion due to exposure to plasma and to quantify the retention and transport properties of tritium in the surface.

Anna GOLUBEVA Kurchatov Institute
Daisuke NISHIJIMA Center for Energy Research, UCSD
Haishan ZHOU Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP)
HIROOKA Yoshihiko Chubu University
Peng WANG Lanzhou Institute of Chemical Physics, Chinese Academy of Sciences
Russell DOERNER Center for Energy Research, UCSD
Vadym MAKHLAI Institute of Plasma Physics, National Science Center "Kharkov Institute of Physics and Technology"
Wolfgang JACOB Max Planck Institute for Plasma Physics (IPP), Garching