Table 1 provides a non-exhaustive summary of ceramic breeder blanket designs, and key parameters, compiled from the references in this chapter. Most of the concepts have a ferritic-martensitic steel as the structural material. Typical values for the expected blanket neutron wall load are about 3 MW m~ , and its lifetime is mostly considered to be limited by about 150 dpa for the structural material. For a DEMO reactor, which is not intended to be a power plant with high availability, typical lithium burnups are 11% (Li4SiO4) or 17% (Li2TiO3), and fast neutron damage in the reduced activation ferritic/ martensitic (RAFM) steels is about 70 dpa.47,48 A typical lifetime for a power reactor blanket is esti­mated to be of the order of 5 years, implying about ten replacements during a 60-year reactor life. The blanket structure should, therefore, be designed with low-activation materials, enabling it to be recycled typically in a period up to 100 years. Such activation requirements have led to Li4SiO4 and Li2TiO3 as the preferred ceramic breeder systems for the European HCPB concept. A case study for Li4SiO4 has been elaborated by Fischer and Tsige-Tamirat.49