Optimization activities on design studies of LHD-type reactor FFHR

A. Sagara, O. Mitarai, T. Tanaka, S. Imagawa, Y. Kozaki, M. Kobayashi, T. Morisaki, T. Watanabe, K. Takahata, H. Tamura, N. Yanagi, K. Nishimura, H. Chikaraishi, S. Yamada, S. Fukada, S. Masuzaki, A. Shishkin, Y. Igitkhanov, T. Goto, Y. OgawaT. Muroga, T. Mito, O. Motojima

研究成果: ジャーナルへの寄稿学術誌査読

52 被引用数 (Scopus)

抄録

Recent activities on optimizing the base design of the large helical device (LHD)-type helical reactor FFHR (force free helical reactor) are presented. Three candidates to secure the blanket space are proposed with the aim of reactor size optimization without deteriorating α-heating efficiency and by taking cost analyses into account. In this way the key engineering aspects are investigated; from 3D blanket designs, it is demonstrated that the peaking factor of the neutron wall loading is 1.2-1.3 and a blanket covering ratio of over 90% is possible by proposing discrete pumping with a semi-closed shield (DPSS) concept. Helical blanket shaping along the divertor field lines is the next big issue. For large superconducting magnet systems under the maximum nuclear heating of 200 W/m3, cable-in-conduit conductor (CICC) and alternative conductor designs are proposed with a robust design of cryogenic support posts. For access to ignited plasmas, new methods are proposed, in which a long rise-up time over 300 s reduces the heating power to 30 MW and a new proportional-integration-derivative (PID) control of the fueling can handle the thermally unstable plasma at high-density operation. This paper focuses on FFHR2m1, which is a modified version of FFHR.

本文言語英語
ページ(範囲)1690-1695
ページ数6
ジャーナルFusion Engineering and Design
83
10-12
DOI
出版ステータス出版済み - 12月 2008

!!!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(全般)
  • 機械工学

フィンガープリント

「Optimization activities on design studies of LHD-type reactor FFHR」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。

引用スタイル