AbstractTritium diffusion and transport behaviour through porous γ-LiAlO2 solid breeder rods of a blanket for a Commercial Tokamak, has been studied for a typical reactor start-up from a “clean” breeder. The proposed tritium transport model accounts for grain diffusion, (using a simplified model), desorption from the surface and pore diffusion, and has been used for the evaluation of the overall characteristic time of the transient tritium release into the helium purge gas. Because of the strong dependence of diffusion and desorption coefficients on temperature, also a detailed thermal analysis has been performed. This study considers a bidimensional axisymmetrical geometry for the blanket and the calculations have been carried out using the general-purpose Finite Element program TRIO E.F.
Research and development of the tritium recovery system for the blanket of the fusion reactor in JAEA