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There have been performed calculation about blanket module, using either solid, liquid, or molten salt material. The aim of the comparison is not only to find the effective configuration for assuring the tritium self-sufficiency condition, but also to predict the material damage rate and the Helium production rate. In the TBR, the liquid/molten salt breeding material resulted a high TBR (>1.15), whereas Iron material as First Wall (FW) component produced a higher Helium concentration, compared to Cr, Mo, W material.