抄録
Recent progress in the Large Helical Device (LHD) experiment during the last 2 yr is reviewed. The LHD has been extending its operational regime toward fusion-relevant conditions while taking advantage of the net-current-free heliotron concept employing a superconducting coil system. Heating capability has exceeded 10 MW, and the central ion and electron temperatures have reached 7 and 10 keV, respectively. The maximum values of beta and pulse length have been extended to 3.2% and 150 s, respectively. Several encouraging phys ics observations have been obtained, i.e., simultaneous achievement of the mitigation of the magnetohydrodynamic instability criteria and good confinement, and formation of an internal transport barrier. The initial results have been obtained using a local island divertor, which shows the possibility of particle control at the plasma edge.
本文言語 | 英語 |
---|---|
ページ(範囲) | 1-12 |
ページ数 | 12 |
ジャーナル | Fusion Science and Technology |
巻 | 46 |
号 | 1 |
DOI | |
出版ステータス | 出版済み - 7月 2004 |
!!!All Science Journal Classification (ASJC) codes
- 土木構造工学
- 核物理学および高エネルギー物理学
- 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