Currently, the most promising fuel for fusion reactors is deuterium–tritium. However, the global inventory of tritium is limited, and this hydrogen isotope has a short half-life; consequently, its availability decreases over time. A key objective of fusion research is, therefore, the development of a self-sufficient reactor. In such a system, the tritium produced within the device can be used to sustain the deuterium–tritium fusion reaction. Tritium production is achieved through a dedicated component, the breeding blanket, by interaction between neutrons and lithium, the breeding blanket generates a tritium surplus with respect to the burned fuel. Several breeding blanket concepts have been proposed and investigated.