Concept of core and divertor plasma for fusion DEMO plant at JAERI

M. Sato, S. Sakurai, S. Nishio, K. Tobita, T. Inoue, Y. Nakamura, K. Shinya, H. Fujieda

研究成果: Conference article

12 引用 (Scopus)

抜粋

Fusion DEMO plant design at JAERI directs toward compactness and economy of the reactor with a fusion output at 3 GW level. The smaller size of the center solenoid (CS) has a large impact on reducing the reactor size and weight. Three candidates for CS, namely "-less", "slim" and "full" CS, are considered according to the role of CS coil that is plasma ramp up and plasma shaping. From points of views of technical feasibility, obtained triangularity (δx) and weight of the reactor, the slim-CS is selected as the candidate for DEMO at JAERI. For slim-CS, high δx (≥0.43), which is enough to suppress giant ELMs, is obtained, and highly radiative outer divertor is required in steady state power handling. The consistent equilibrium was found to satisfy the divertor requirements and radial build. During the plasma current ramp up phase, the acceleration voltage of neutral beam injection (NBI) has to be changed more than two times. In order to inject sufficient power during the low-energy beam injection, the present technology must be replaced by a new constant-current, variable-voltage technology.

元の言語English
ページ(範囲)1277-1284
ページ数8
ジャーナルFusion Engineering and Design
81
発行部数8-14 PART B
DOI
出版物ステータスPublished - 2006 2 1
外部発表Yes
イベントProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B -
継続期間: 2005 5 222005 5 27

ASJC Scopus subject areas

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

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    Sato, M., Sakurai, S., Nishio, S., Tobita, K., Inoue, T., Nakamura, Y., Shinya, K., & Fujieda, H. (2006). Concept of core and divertor plasma for fusion DEMO plant at JAERI. Fusion Engineering and Design, 81(8-14 PART B), 1277-1284. https://doi.org/10.1016/j.fusengdes.2005.09.074