Nuclear analysis of DEMO water-cooled blanket based on sub-critical water condition

C. Liu, K. Tobita, H. Utoh, Y. Someya, H. Takase, N. Asakura

Research output: Contribution to journalArticlepeer-review

13 Citations (Scopus)


For the water-cooled solid blanket of DEMO, the nuclear analysis was performed based on present cooling piping system. Especially, distributions of neutron load and temperature were calculated with Pn is 5 MW/m 2. Furthermore, the local TBR was optimized by changing the material proportion for each Pn level (1-5 MW/m2). It was confirmed that the size of cooling loop for sub-critical water could be used as about 2000 × 450 mm and the cooling pipe diameter of D is 12 mm, d is 9 mm at v is 5.36 m/s. The pipe pitches would vary with Pn level which is related to the blanket structure design. Nuclear heat distribution is the base to decide the distribution of cooling pipe positions. It was found that the local TBR of blanket would be dropped down along with the Pn level rising which was mainly depended on the thickness of beryllium variation. Finally, the layout of cooling pipes for each level was obtained.

Original languageEnglish
Pages (from-to)2839-2842
Number of pages4
JournalFusion Engineering and Design
Issue number12
Publication statusPublished - 2011 Dec
Externally publishedYes


  • Nuclear analysis
  • Solid blanket
  • Water-cooled

ASJC Scopus subject areas

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


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