Analysis of the Breeder Blanket Interface for a liquid lithium blanket

To design and incorporate a breeder blanket interface (BBI) at TSTA, a study was begun to define the product streams from representative breeder blankets (liquid metal, aqueous salt solution, and solid breeder). The evaluation of the product stream for self-cooled liquid Li is described. Possible methods of tritium recovery were compared; molten salt extraction was selected as the reference method. The levels of impurities and radionuclides in the extraction system were estimated and their transport in the recovery system was calculated. The T product stream was 99.5% helium. The H/T isotropic ratio was 0.4. The major non-He impurity was nitrogen. The stream also contained corrosive halides, small amounts of certain radionuclides, C-14, P-32, and S-35, ammonia and acetylene. . 77 ref.--AA