Conceptual design activities and key issues on LHD-type reactor FFHR

A. Sagara, O. Mitarai, S. Imagawa, T. Morisaki, T. Tanaka, N. Mizuguchi, T. Dolan, J. Miyazawa, K. Takahata, H. Chikaraishi, S. Yamada, K. Seo, R. Sakamoto, S. Masuzaki, T. Muroga, H. Yamada, S. Fukada, H. Hashizume, K. Yamazaki, T. MitoO. Kaneko, T. Mutoh, N. Ohyabu, N. Noda, A. Komori, S. Sudo, O. Motojima

研究成果: Article査読

46 被引用数 (Scopus)


An overview of conceptual design activities on the LHD-type helical reactor FFHR is presented, mainly focusing on optimization studies on the reactor size and the proposal of a long-life blanket. A major radius of around 15 m is the present candidate under the constraints of the energy confinement achieved in LHD, a maximum magnetic field around 13 T with a current density around 30 A/mm2 and a neutron wall loading around 1.5 MW/m2. R&D on super-conducting magnet systems of large scale, high field and high current-density are new challenging targets based on the LHD. The development of new design tools has been started aiming at establishing a virtual power plant (VPP) and a virtual reality system for 3D design assisting. Next design issues are mainly on engineering optimization of the first wall thickness, the detailed 3D blanket system, and unscheduled replacements of breeder blankets.

ジャーナルFusion Engineering and Design
出版ステータスPublished - 2006 11月

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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