Evaluation method of tritium breeding ratio using neutron transport equation

Hideaki Matsuura, Masabumi Nishikawa

研究成果: 書籍/レポート タイプへの寄稿

抄録

The breeding blanket is the only place to produce tritium (T) in a fusion reactor. It is necessary to recover bred T in the blanket effectively because no T in the natural resources is usable as the fuel in a fusion reactor. Fortunately, T can be produced by the reaction between neutron and lithium in the blanket placed surrounding the fusion chamber with. The T breeding ratio attainable in the blanket should be large enough to cover whole T consumed for steady operation of a fusion reactor. In this chapter, T breeding in a blanket zone and the evaluation method of the T breeding ratio are introduced.

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257-272
ページ数16
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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