Considerable progress has been made in the last few years in divertor physics. This progress enables confidence in being able to meet the ITER requirement of 5 MW/m² peak heat load to the divertor surface, which when coupled with the engineering result of projected 10 MW/m² capability, allows an effective operating window for ITER. The two basic features of the ITER divertor solution, an extended radiating region in the divertor and a reduction of parallel heat flux by about a factor of five, have been demonstrated in experiments using a variety of techniques. The detached plasma regime has been extensively documented; this regime lowers the particle flux to the divertor plates to keep the recombination power in the plate below 5 MW/m². In fact, very low temperature (Te ~ 1-2 eV) divertor plasmas have been found in which the plasma exhibits about 50% recombination in the divertor plasam volume. Regimes with a high core radiation fraction have also been found compatible with good core confinement. Good core confinement and detached divertor plasmas are not generally found in today's experiments, but on the basis of dimensionless parameter arguments, it is perhaps not necessary to do so. The regimes of high core plasma density and detached divertors do seem to intersect in ITER. An understanding of the density limit in tokamaks is emerging; the empirical density limit has been exceeded while retaining good confinement. Good progress continues to be made on developing physics approaches to even more divertor radiation. Experiments show that helium exhaust should be adequate in ITER. Erosion of the divertor surfaces owing to Edge Localized Mode heat pulses remains marginal. Recent new divertor configurations in the major tokamaks have begun to produce results.