Abstract
Tritium is the fuel for the future magnetic-confined fusion devices that requires accurate simulation investigation. A generic multi-physics model is implemented in this work to analyze the tritium transport behaviors in the fusion reactor components. The model is applied to evaluate plasma-induced tritium permeation and retention in the first wall (FW) of the water-cooled ceramics breeder blanket under typical operational conditions for the China Fusion Engineering Test Reactor. The total amount of tritium retention and permeation due to ion-implantation is obtained for different reactor power levels. The impact on the tritium transport behaviors from the Soret effect is also analyzed. Simulation results suggest that the tungsten armor can be a dominating source of mobile tritium retention in comparison to the steel structure in the FW; and that the Soret effect would impact the amount of tritium permeated into the coolant, in a favorable way.
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