Abstract
Three notable experimental results regarding plasma-material interaction between actual tokamak plasmas and high and low Z materials (tungsten and carbon) are reviewed. In the ASDEX-U, a center column was covered by tungsten, and its effects on plasma performance and erosion-redeposition behavior of tungsten were studied. In the TEXTOR, a twin-limiter composed half of tungsten and half of graphite was inserted in the edge plasma to study the difference of plasma material interaction between carbon and tungsten. In the JT-60U, detailed measurements of erosion and redeposition of graphite divertor plates revealed the transport of eroded carbon atoms in edge plasmas.
