Design studies of helical-type fusion reactor FFHR

A. Sagara, O. Motojima, S. Imagawa, O. Mitarai, T. Noda, T. Uda, K. Watanabe, H. Yamanishi, H. Chikaraishi, A. Kohyama, H. Matsui, T. Muroga, N. Noda, N. Ohyabu, T. Satow, A. A. Shishkin, Dai Kai Sze, A. Suzuki, S. Tanaka, T. TeraiK. Yamazaki, J. Yamamoto

Research output: Contribution to journalArticlepeer-review

23 Citations (Scopus)


The main feature of FFHR is force-free-like configuration of helical coils, which makes it possible to simplify the coil supporting structure and to use high magnetic field instead of high plasma beta. The other feature is the selection of molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety. Collaboration works based on the LHD project have made great progress in the reactor studies by focusing on engineering aspects of the high magnetic field and Flibe system design. Encouraging positive results are shown on ignition access, mechanical stress in coils supporting structures, improvement in the blanket system including materials selection and tritium recovery. Critical issues on fundamental safety analysis and maintainability of reactor components are also discussed, and many subjects are pointed out as future works.

Original languageEnglish
Pages (from-to)349-355
Number of pages7
JournalFusion Engineering and Design
Issue number1-4
Publication statusPublished - 1998 Sept 1

ASJC Scopus subject areas

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


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