An operational scenario has been demonstrated on the DIII-D tokamak where the graphite covered divertor is free ofnet erosion. Reduction of divertor carbon erosion is accomplishedusing a low temperature (detached) divertor plasma that eliminatesphysical sputtering. Likewise, the carbon influx arising from chemicalerosion is found to be very low in the detached divertor, althoughuncertainties exist concerning chemical erosion yield due to theunknown effect of detachment on hydrocarbon transport. Nearstrike point regions, the rate of carbon deposition is ≈ 3 cm/burn-year,with a corresponding hydrogenic co-deposition rate greater than 1 kg/(m2burn-year);rates which are problematic for steady state fusion reactors. Thecarbon net deposition rate in the divertor is consistent with carbonarriving from the core plasma region. Carbon ion influx from the mainwall is measured to be relatively large in the high density detachedregime and is of sufficient magnitude to account for the depositionrate in the divertor. Divertor redeposition is, therefore, determinedby non-divertor erosion and transport. Despite the success in reducingdivertor erosion on DIII-D with detachment, no significant reductionis found in the core plasma carbon density, illustrating theimportance of non-divertor erosion and the complex coupling betweenerosion/re-deposition and impurity plasma transport.