Recovery of tritium bred in blanket

Kazunari Katayama, Masabumi Nishikawa

Research output: Chapter in Book/Report/Conference proceedingChapter

1 Citation (Scopus)


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.

Original languageEnglish
Title of host publicationTritium
Subtitle of host publicationFuel of Fusion Reactors
PublisherSpringer Japan
Number of pages22
ISBN (Electronic)9784431564607
ISBN (Print)9784431564584
Publication statusPublished - Jan 1 2016

All Science Journal Classification (ASJC) codes

  • General Engineering
  • General Environmental Science


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