Modeling of Impurity Transport in Edge Plasmas and Tritium Codeposition on Plasma Facing Walls in ITER

Abstract

In order to simulate carbon deposition profile in the divertor of ITER, long-distance transport in the scrape-off-layer and divertor plasma of carbon and hydrocarbons eroded from the divertor target plates are modeled. Physically eroded carbons dominate a sharp profile on the outer target plate, whereas at the inner target plate, a very small redeposition is observed. Chemically eroded hydrocarbons produce a redeposition on the dome area as well as both inner and outer target plates. Assuming tritium content in the redeposited layers, tritium co-deposition profile on the inner and outer target plates and dome is estimated, which allows us to predict the long-term tritium retention in the divertor of ITER.