Evaluation method of tritium breeding ratio using neutron transport equation

Hideaki Matsuura, Masabumi Nishikawa

Research output: Chapter in Book/Report/Conference proceedingChapter

Abstract

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.

Original languageEnglish
Title of host publicationTritium
Subtitle of host publicationFuel of Fusion Reactors
PublisherSpringer Japan
Pages257-272
Number of pages16
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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