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For many years a research program on lithium metazirconate has been underway in the framework between ENEA and the Department of Applied Chemistry and Science of Materials (Bologna University). This research is aimed to verify the possibility of using such material as a breeder in future nuclear fusion reactors. The research program includes studies on nuclear properties and experimental work on the development of fabrication methods and the characterization of sintered samples, with the aim to verify that lithium metazirconate has the nuclear, physical, chemical, and mechanical properties able to satisfy the requested performance in the blanket of a fusion reactor. The metazirconate is developed as an alternative to other breeding materials, such as (gamma) -aluminate and silicates. One of the most interesting properties of the zirconate, as compared to the other candidate materials, regards its better behavior in releasing tritium; this very favorable characteristic is the main incentive for strengthening the research. In the choice of a breeding material, it is necessary to take into account all relevant characteristics, also including nuclear properties. The paper describes the results obtained experimentally and by calculation on the main physical and nuclear properties of lithium metazirconate.
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