A full tungsten (W) divertor is proposed for plasma and power exhaust in ITER. Because of the high specific radiation power of W at fusion plasma temperatures and correspondingly low permitted concentrations of < O (10-5), the quantification of W sources and transport from the divertor into the core are important issues for reliable tokamak operation. The ITER-like Wall at JET with beryllium (Be) in the main chamber and W in the divertor as well as the all W ASDEX Upgrade (AUG) are suitable for studying ITER-relevant aspects of W-erosion as well as power-handling. This contribution aims to elucidate W erosion in relation to divertor plasma parameters and impurity composition allowing extrapolation toward ITER.