Recovery of tritium bred in blanket

Kazunari Katayama, Masabumi Nishikawa

Research output: Chapter in Book/Report/Conference proceedingChapter

1 Citation (Scopus)

Abstract

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
Pages273-294
Number of pages22
ISBN (Electronic)9784431564607
ISBN (Print)9784431564584
DOIs
Publication statusPublished - Jan 1 2016

All Science Journal Classification (ASJC) codes

  • Engineering(all)
  • Environmental Science(all)

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