An Experiment to Tame the Plasma Material Interface

Approaches to heat flux handling and tritium retention that may work for ITER do not generally extrapolate to Demo, and certain ITER parameters, such as first-wall temperature and loss power / major radius do not approach those of Demo. Thus research will be required in parallel with ITER to bridge the gap to Demo. A series of key questions sets the requirements for the research capabilities of a device fill this gap, such as heating power / major radius, flexibility in poloidal field configuration, plasma facing component flexibility in materials (solid and liquid) and in temperature, plasma pulse length, and access for surface and plasma diagnostics.