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

Research output: Contribution to journalConference articlepeer-review

6 Citations (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.

Original languageEnglish
Pages (from-to)1299-1304
Number of pages6
JournalFusion Engineering and Design
Issue number8-14 PART B
Publication statusPublished - 2006 Feb
EventProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B -
Duration: 2005 May 222005 May 27


  • Flibe blanket
  • Graphite
  • Helical reactor
  • Neutron irradiation
  • Thermal conductivity


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