Damage of the first wall in a plasma simulator and in the TCA tokamak: Implications for theoretical models of hydrogen recycling

In order to provide data for a more realistic model of hydrogen recycling in devices for controlled nuclear fusion research the structural damage of the near surface region of the first wall has been investigated. Very high density of defects has been found within the surface layer of a thickness much larger than the projected range of the impinging ions. Preliminary interpretation of these results is given and their implications for the theoretical models of hydrogen recycling are discussed. (orig.)