Investigation of compatibility of low activation ferritic steel with high performance plasma by full covering of inside vacuum vessel wall on JFT-2M

K. Tsuzuki, K. Shinohara, K. Kamiya, H. Kawashima, M. Sato, G. Kurita, M. Bakhtiari, H. Ogawa, K. Hoshino, S. Kasai, K. Uehara, Y. Kusama, M. Yamamoto, T. Shibata, K. Kikuchi, H. Tsutsui, R. Shimada, T. Hino, Y. Hirohata, A. AmemiyaY. Sadamoto, Y. Nagashima, A. Ejiri

研究成果: ジャーナルへの寄稿会議記事査読

8 被引用数 (Scopus)

抄録

Low activation ferritic steel plates were installed in the JFT-2M tokamak to fully cover the inside wall of the vacuum vessel (ferritic inside wall; FIW) as a simulation of the blanket wall of the fusion demonstration reactor. After the physics and engineering design concerns with the ripple reduction, the electro-magnetic force and so on, FIW was installed with a tolerance of a few mm. The ripple reduction was confirmed from the detailed measurement. Tokamak discharges were obtained without changing control system, as predicted theoretically. The reduction of ripple loss of fast ions was clearly demonstrated by both experiments and calculations. Compatibility of FIW with high normalized beta plasma up to 3.3 was demonstrated at relatively far wall position. Preliminary investigation showed that the slowdown of the growth rate occurred with closer wall position, which presumably corresponds to wall stabilization effect.

本文言語英語
ページ(範囲)721-725
ページ数5
ジャーナルJournal of Nuclear Materials
329-333
1-3 PART A
DOI
出版ステータス出版済み - 8月 1 2004
外部発表はい
イベントProceedings of the 11th Conference on Fusion Research - Kyoto, 日本
継続期間: 12月 7 200312月 12 2003

!!!All Science Journal Classification (ASJC) codes

  • 核物理学および高エネルギー物理学
  • 材料科学(全般)
  • 原子力エネルギーおよび原子力工学

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