Search for reality of solid breeder blanket for DEMO

K. Tobita, H. Utoh, C. Liu, H. Tanigawa, D. Tsuru, M. Enoeda, T. Yoshida, N. Asakura

Research output: Contribution to journalArticlepeer-review

37 Citations (Scopus)


For a tokamak fusion DEMO reactor with the fusion output of 2.95 GW, neutronic and thermal design of blanket is under way to find a feasible blanket concept. For the continuity with the Japanese ITER-TBM options, this study considered water-cooled blanket with solid breeding materials of Li ceramics (Li4SiO4, Li2TiO3 and Li 2ZrO3) and Be multipliers (Be and Be12Ti). Based on a neutronics-heat coupled analysis, the tritium breeding ratio was evaluated so as to satisfy constraints of the operating temperature of ≤900°C for Li ceramics and Be12Ti, and ≤600°C for Be. Cooling water condition was assumed to be 23MPa and 290-360°C. The result indicates that surplus tritium production in lower neutron wall load (P n) blanket compensates a shortfall in higher Pn blanket and thus the overall tritium production can marginally satisfy fuel self-sufficiency.

Original languageEnglish
Pages (from-to)1342-1347
Number of pages6
JournalFusion Engineering and Design
Issue number7-9
Publication statusPublished - 2010 Dec
Externally publishedYes


  • Blanket
  • DEMO
  • SlimCS
  • Solid breeder
  • TBR

ASJC Scopus subject areas

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


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