Abstract
Lithium-containing ceramics were quickly recognized as promising tritium breeding materials for fusion reactor blankets, particularly because of their safety advantages. Relevant material properties were investigated to evaluate further their suitability. An extensive R&D program complemented a conceptual blanket design activity either for near-term machines or for power reactors. All aspects were addressed: fabricability; overall properties (baseline, thermal, mechanical); compatibility with structures and beryllium; tritium release characteristics; irradiation behavior; activation; reprocessing; waste disposal issues. As a result of this investigation, lithium-containing ceramics are considered to be excellent tritium breeding materials.
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