In order to ensure tritium (T) fuel self-sufficiency in a fusion power plant, key issues are full recovery of T generated in breeder materials and minimization of T loss in all fuel cycle systems. To realize the full recovery, T behavior in the breeder materials has to be understood, and the optimal T extraction system has to be designed. In this chapter, firstly, solid breeder materials and liquid breeder materials are introduced. Then, characteristics of T release from the solid breeder materials are explained, and a T release model is introduced. Finally, tritium extraction from liquid breeder materials is briefly explained.
CITATION STYLE
Katayama, K., & Nishikawa, M. (2016). Recovery of tritium bred in blanket. In Tritium: Fuel of Fusion Reactors (pp. 273–294). Springer Japan. https://doi.org/10.1007/978-4-431-56460-7_13
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