Recovery of tritium bred in blanket

Kazunari Katayama, Masabumi Nishikawa

Research output: Chapter in Book/Report/Conference proceedingChapter

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

Fingerprint

tritium
Tritium
Recovery
liquid
self sufficiency
Liquids
material
power plant
Power plants
Fusion reactions

All Science Journal Classification (ASJC) codes

  • Engineering(all)
  • Environmental Science(all)

Cite this

Katayama, K., & Nishikawa, M. (2016). Recovery of tritium bred in blanket. In Tritium: Fuel of Fusion Reactors (pp. 273-294). Springer Japan. https://doi.org/10.1007/978-4-431-56460-7_13

Recovery of tritium bred in blanket. / Katayama, Kazunari; Nishikawa, Masabumi.

Tritium: Fuel of Fusion Reactors. Springer Japan, 2016. p. 273-294.

Research output: Chapter in Book/Report/Conference proceedingChapter

Katayama, K & Nishikawa, M 2016, Recovery of tritium bred in blanket. in Tritium: Fuel of Fusion Reactors. Springer Japan, pp. 273-294. https://doi.org/10.1007/978-4-431-56460-7_13
Katayama K, Nishikawa M. Recovery of tritium bred in blanket. In Tritium: Fuel of Fusion Reactors. Springer Japan. 2016. p. 273-294 https://doi.org/10.1007/978-4-431-56460-7_13
Katayama, Kazunari ; Nishikawa, Masabumi. / Recovery of tritium bred in blanket. Tritium: Fuel of Fusion Reactors. Springer Japan, 2016. pp. 273-294
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