Ceramic materials are under investigation as potential breeder material in fusion reactors. This paper will review candidate materials with respect to (a) fabrication routes and characterization, (b) properties in as-fabricated and irradiated condition, and (c) experimental results from laboratory and in-pile investigations on tritium transport and release. Also discussed are the resources of beryllium, which is being considered as a neutron multiplier. The comparison of ceramic properties that is attempted here aims at the identification of the most-promising material for use in a tritium breeding blanket.