AbstractThe International Thermonuclear Experimental Reactor (ITER) breeding blanket is designed to breed the necessary tritium for ITER operation during the enhanced performance phase by replacing the shielding blanket of the basic performance phase. Similar to the shielding blanket, it has to remove the majority of the fusion power generated by the plasma and to protect the vacuum vessel and the toroidal field coils from excessive nuclear heating and radiation damage. It has to produce a net tritium breeding ratio of more than 0.8 to satisfy the technical objectives of the enhanced performance phase. For compatibility with the ITER design and to satisfy the blanket functional requirements, a water-cooled modular solid breeder blanket with a beryllium neutron multiplier has been selected. Lithium zirconate is the reference breeder material based on the current database. Enriched lithium is used to enhance the tritium breeding capability, to reduce the radial blanket thickness, to decrease the breeder material volume, to lower the breeder thermal stresses, and to enhance the shielding capability. Similar to the shielding blanket, the breeding blanket uses Type 316LN-IG austenitic steel structural material. Both forms of beryllium material, porous and pebbles, are used at different blanket locations based on design requirements. This paper is concerned with the design analyses and design selections, including beryllium form, breeder material, tritium breeding, and heat transfer across the beryllium–steel interface. Also, the required research and development tasks for the ITER breeding blanket are summarized.