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Engineering design and control scenario for steady-state high-beta operation in National Centralized Tokamak

  • K. Tsuchiya
  • , M. Akiba
  • , H. Azechi
  • , T. Fujii
  • , T. Fujita
  • , M. Fujiwara
  • , K. Hamamatsu
  • , H. Hashizume
  • , N. Hayashi
  • , H. Horiike
  • , N. Hosogane
  • , M. Ichimura
  • , K. Ida
  • , Y. Ikeda
  • , T. Imai
  • , N. Inoue
  • , S. Ishida
  • , S. Itoh
  • , Y. Kamada
  • , H. Kawashima
  • M. Kikuchi, A. Kimura, K. Kizu, H. Kubo, Y. Kudo, K. Kurihara, G. Kurita, M. Kuriyama, K. Masaki, M. Matsukawa, M. Matsuoka, Y. Miura, Y. M. Miura, N. Miya, A. Morioka, K. Nakamura, H. Ninomiya, A. Nishimura, K. Okano, K. Okuno, A. Sagara, M. Sakamoto, S. Sakurai, K. Sato, R. Shimada, A. Shimizu, T. Suzuki, H. Takahashi, Y. Takase, M. Takechi, H. Tamai, S. Tanaka, H. Tsutsui, Y. Uesugi, K. Yatsu, N. Yoshida

研究成果: ジャーナルへの寄稿 › 会議記事 › 査読

抄録

The mission of the National Centralized Tokamak (NCT) is to establish high-beta steady-state plasma operation for DEMO and to contribute to ITER. Plasma performance with high-beta conditions is discussed. It is found that near break-even class plasma (QDTeq≥0.7) with high beta (βN ≥ 3.5) is achievable with 25 MW of NB power at IP = 4.0 MA and an aspect ratio of 2.6. High beta with steady-state full current drive is possible with 13 MW of NB power at IP = 1.5-1.7 MA. In the engineering design activity of NCT, the strength of the support structure and strength of material for the conductor is confirmed for the superconducting coils, and the successful progress of R&D of boron-loaded resin for neutron shielding is discussed.

本文言語英語
ページ(範囲)1599-1605
ページ数7
ジャーナルFusion Engineering and Design
巻81
号8-14 PART B
DOI
出版ステータス出版済み - 2月 2006
イベントProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B -
継続期間: 5月 22 2005 → 5月 27 2005

!!!All Science Journal Classification (ASJC) codes

  • 土木構造工学
  • 原子力エネルギーおよび原子力工学
  • 材料科学一般
  • 機械工学

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