Simplification of blanket system for SlimCS fusion DEMO reactor

Youji Someya, Haruhiko Takase, Hiroyasu Utoh, Kenji Tobita, Changle Liu, Nobuyuki Asakura

Research output: Contribution to journalArticlepeer-review

35 Citations (Scopus)


Simplification of blanket system is necessary for a fusion DEMO reactor. Although the conceptual design of a tritium-breeding blanket for SlimCS has been studied in the past several years, the structure of the previous blanket seems to be complex and difficult to manufacture from the viewpoint of engineering. In this paper, we proposed simplification of blanket structure without decreasing the net Tritium Breeding Ratio (TBR). In the proposed concept, the blanket is filled with the mixture of Li4SiO4 pebbles or Li 2O pebbles for the tritium breeding and Be12Ti pebbles for the neutron multiplication. To confirm the effectiveness of this concept, an ANIHEAT code with the nuclear library FENDL-2.0 was used for calculations of the neutronic and thermal analyses. The result indicated that, under the constraint of the blanket thickness being less than 0.5 m, the mixture of Li2O pebbles and Be12Ti ones is the most effective and that the TBR is expected to be greater than 1.05.

Original languageEnglish
Pages (from-to)2269-2272
Number of pages4
JournalFusion Engineering and Design
Issue number9-11
Publication statusPublished - 2011 Oct 1
Externally publishedYes


  • Demo
  • Mixed breeder blanket
  • Neutronics
  • SlimCS
  • Thermal analysis

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering


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