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.
|Title of host publication||Tritium|
|Subtitle of host publication||Fuel of Fusion Reactors|
|Number of pages||22|
|Publication status||Published - Jan 1 2016|
All Science Journal Classification (ASJC) codes
- Environmental Science(all)