Tritium Transport Model at the Breeder Module Level for a Water-Cooled Ceramic Breeder Blanket for the CFETR

Abstract

The tritium self-sufficiency concept has been pursued with the development of fusion energy, which requires tritium treatment and recovery. Accordingly, the tritium transport characteristics in a breeder blanket are crucial to predict the tritium inventories and permeation. In the present work, a multiphysics coupling analysis model for a water-cooled ceramic breeder (WCCB) blanket was built, providing a method to conduct a comprehensive assessment of the tritium transport behaviors in the blanket, including the tritium concentration, tritium inventory, and tritium permeation through the structural material to the coolant. Bulk diffusion and surface processing of tritium in the blanket are considered, and the isotope exchange reaction in the purge gas and the effect of the hydrogen content on the tritium transport behavior are also considered. These results indicate that hydrogen plays a significant role in reducing the tritium inventory and permeation.