Consideration on blanket structure for fusion DEMO plant at JAERI

S. Nishio, J. Ohmori, T. Kuroda, K. Tobita, M. Enoeda, D. Tsuru, T. Hirose, S. Sato, Y. Kawamura, H. Nakamura, M. Sato

研究成果: Conference article査読

22 被引用数 (Scopus)


Our idea on the DEMO plant is that it must demonstrate (1) an electric power generation of one GW level, (2) self-sufficiency of tritium fuel (TBR is more than 1.05), (3) year-long continuous operation, etc. At the same time, DEMO is expected to use technologies to be proven by 2020 and present an economical prospect of fusion energy in the operational time of the reactor. The design guidelines for the blanket are defined in order to meet the mission of the DEMO plant as mentioned above. Major design conditions are surface heat flux of 0.5 MW/m 2 with peaking factor of 2, a neutron wall load of 3.5 MW/m 2 with peaking factor of 1.5 and a neutron fluence of about 10 MW/m 2. To moderate the technological extrapolation, reduced activation ferritic steel (F82H) structural material, Li 2TiO 3 and Be neutron multiplier are considered. To improve the economical aspect, supercritical water with inlet/outlet temperatures of 280/510 °C is chosen as coolant material, with coolant pressure of 25 MPa. As a result, a thermal efficiency of 41% is achieved. To obtain higher plasma performance, MHD instabilities suppressing shell structure is adopted with structural compatibility to the blanket structure. To meet higher plant availability requirements (more than 75%), the hot cell maintenance approach is selected for the replaceable power core components.

ジャーナルFusion Engineering and Design
8-14 PART B
出版ステータスPublished - 2006 2
イベントProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B -
継続期間: 2005 5 222005 5 27

ASJC Scopus subject areas

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

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