Recovery of tritium bred in blanket

Kazunari Katayama, Masabumi Nishikawa

研究成果: 書籍/レポート タイプへの寄稿

1 被引用数 (Scopus)

抄録

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.

本文言語英語
ホスト出版物のタイトルTritium
ホスト出版物のサブタイトルFuel of Fusion Reactors
出版社Springer Japan
ページ273-294
ページ数22
ISBN(電子版)9784431564607
ISBN(印刷版)9784431564584
DOI
出版ステータス出版済み - 1月 1 2016

!!!All Science Journal Classification (ASJC) codes

  • 工学(全般)
  • 環境科学(全般)

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