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

研究成果: Article査読

23 被引用数 (Scopus)

抄録

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.

本文言語English
ページ(範囲)349-355
ページ数7
ジャーナルFusion Engineering and Design
41
1-4
DOI
出版ステータスPublished - 1998 9 1

ASJC Scopus subject areas

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

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