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

Fingerprint

Fusion reactors
tritium
Tritium
Neutrons
breeding
Breeding blankets
Natural resources
Lithium
Fusion reactions
lithium
natural resource
evaluation method
reactor

All Science Journal Classification (ASJC) codes

  • Engineering(all)
  • Environmental Science(all)

Cite this

Matsuura, H., & Nishikawa, M. (2016). Evaluation method of tritium breeding ratio using neutron transport equation. In Tritium: Fuel of Fusion Reactors (pp. 257-272). Springer Japan. https://doi.org/10.1007/978-4-431-56460-7_12

Evaluation method of tritium breeding ratio using neutron transport equation. / Matsuura, Hideaki; Nishikawa, Masabumi.

Tritium: Fuel of Fusion Reactors. Springer Japan, 2016. p. 257-272.

Research output: Chapter in Book/Report/Conference proceedingChapter

Matsuura, H & Nishikawa, M 2016, Evaluation method of tritium breeding ratio using neutron transport equation. in Tritium: Fuel of Fusion Reactors. Springer Japan, pp. 257-272. https://doi.org/10.1007/978-4-431-56460-7_12
Matsuura H, Nishikawa M. Evaluation method of tritium breeding ratio using neutron transport equation. In Tritium: Fuel of Fusion Reactors. Springer Japan. 2016. p. 257-272 https://doi.org/10.1007/978-4-431-56460-7_12
Matsuura, Hideaki ; Nishikawa, Masabumi. / Evaluation method of tritium breeding ratio using neutron transport equation. Tritium: Fuel of Fusion Reactors. Springer Japan, 2016. pp. 257-272
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