Carbon tiles as spectral-shifter for long-life liquid blanket in LHD-type reactor FFHR

A. Sagara, S. Imagawa, T. Tanaka, T. Muroga, Y. Kubota, T. Dolan, H. Hashizume, T. Kunugi, S. Fukada, A. Shimizu, T. Terai, O. Mitarai

研究成果: Conference article査読

6 被引用数 (Scopus)


In terms of engineering feasibility for long-life Flibe blanket in LHD-type reactor FFHR, the Spectral-shifter and Tritium breeder Blanket (STB) concept is evaluated by taking neutron irradiation effects into account under system integration such as Flibe cooling and components replacement. FEM calculations for the neutron wall loading of 1.5 MW/m2 show that the temperature of the STB armor tile can be kept below 2000 K by optimizing the first metal wall thickness. The heat load experiment on the STB armor mockup confirms feasibility of the temperature control and mechanical joining. Degradation of STB armor tiles due to neutron irradiation requires replacement of them every few years by means of remote handling "screw coasters" using helical winding, where the replaced tiles are low level wastes. Although the STB concept is feasible within nuclear and thermal properties, more detailed structural optimization is needed including the mechanical and chemical properties.

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

ASJC Scopus subject areas

  • 土木構造工学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 機械工学


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