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.
The Comparison Experiment for the Sputtering of Steel (CESS) is a project within this project to perform a set of coordinated experiments on steel surfaces to compare sputtering yields in different experimental devices.
|Max Planck Institute for Plasma Physics, Garching, Germany|
|National Institute for Fusion Science, Japan|
|Lanzhou Institute of Chemical Physics, Chinese Academy of Sciences, China|
|Kurchatov Institute, Russia|
|Center for Energy Research, UCSD, United States of America|
|Institute of Plasma Physics, Kharkov Institute of Physics and Technology, Ukraine|
|SCK CEN, Belgium|
|Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP), China|