Fusion Science and Technology / Volume 60 / Number 4 / November 2011 / Pages 1467-1470
Interaction with Materials / Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) / dx.doi.org/10.13182/FST11-A12708
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.