AbstractSeveral ceramic breeder blanket concepts for fusion experimental reactors have been proposed. Satisfying the allowable temperature ranges of each material and enhancing the tritium breeding ratio (TBR) are indispensable to development of any blanket concept. The present paper proposes a ceramic breeder blanket concept which realizes these points. Lithium zirconate (Li2ZrO3) is adopted as the breeder along with double-cladding pins having hollow pellets. The pellets are placed in the co-axial center tubes, while beryllium pebbles fill the outer tubes and serve not only as a neutron multiplier but also as a thermal barrier between the breeder and coolant, which flows outside the pins. The pins can be shortened and straightened by setting them in the toroidal direction. Hollow pellets are used to unify the radii of the outer clad, and reduce the volume fraction of stainless steel by making baffle plates unnecessary between the pin rows. The optimum ratio of the Li2ZrO3 volume fraction to the beryllium plus Li2ZrO3 one is investigated to maximize the TBR, and the pin radii and pin arrangement are determined. The proposed blanket concept is seen to satisfy the temperature ranges and enhance the local TBR to 1.3.