Mass, (lo6 g) Volume, (m3) Thickness, (cm) T. Gen. Rate, (g/day) Abstract: This paper presents quantitative predict,ions for the tritium release and inventory in a water-cooled solid breeder blanket for the International Thermonuclear Experimental Reactor (ITER) obtained from the tritium transport code MISTRAL [l] recently developed at UCLA. The blanket consists of a layout assembly of solid br...