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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