Design optimization for plasma performance and assessment of operation regimes in JT-60SA

被引：26

作者：

Fujita, T. ^{[1
]}

Tamai, H. ^{[1
]}

Matsukawa, M. ^{[1
]}

Kurita, G. ^{[1
]}

Bialek, J. ^{[2
]}

Aiba, N. ^{[1
]}

Tsuchiya, K. ^{[1
]}

Sakurai, S. ^{[1
]}

Suzuki, Y. ^{[1
]}

Hamamatsu, K. ^{[1
]}

Hayashi, N. ^{[1
]}

Oyama, N. ^{[1
]}

Suzuki, T. ^{[1
]}

Navratil, G. A. ^{[2
]}

Kamada, Y. ^{[1
]}

Miura, Y. ^{[1
]}

Takase, Y. ^{[3
]}

Campbell, D. ^{[4
]}

Pamela, J. ^{[5
]}

Romanelli, F. ^{[6
]}

Kikuchi, M. ^{[1
]}

机构：

[1] Japan Atom Energy Agcy, Naka, Ibaraki 3110193, Japan

[2] Columbia Univ, New York, NY 10027 USA

[3] Univ Tokyo, Kashiwa, Chiba 2778561, Japan

[4] EFDA Close Support Unit, D-85748 Garching, Germany

[5] Culham Sci Ctr, EFDA JET Close Support Unit, Abingdon OX14 3DB, Oxon, England

[6] CR Frascati, EURATOM Assoc, ENEA Fus, I-00044 Frascati, Italy

来源：

NUCLEAR FUSION | 2007年 / 47卷 / 11期

关键词：

D O I：

10.1088/0029-5515/47/11/013

中图分类号：

O35 [流体力学]; O53 [等离子体物理学];

学科分类号：

070204 ; 080103 ; 080704 ;

摘要：

The design of the modification of JT-60U, JT-60SA has been optimized from the viewpoint of plasma performance, and operation regimes have been evaluated with the latest design. Upper and lower divertors with different geometries will be prepared for flexibility of the plasma shape, which will enable both low aspect ratio (A similar to 2.65) and ITER shape (A = 3.1) configurations. The beam lines of negative-ion neutral beam injection will be shifted downwards by similar to 0.6 m for the off-axis current drive (CD), in order to obtain a weak/reversed shear plasma, as well as having the capability of heating the central region. The feedback control coils along the openings in the stabilizing plate are found effective in suppressing the resistive wall mode and sustaining high beta(N) close to the ideal wall limit. Sustainment of plasma current of 3-3.5 MA for 100 s will be possible in ELMy H-mode plasmas with moderate heating power, beta(N), and density within an available flux swing. It is also expected that higher beta(N), high-density ELMy H-mode plasmas will be maintained for 100 s with higher heating power. The expected regime of full CD operation has been extended with upgraded heating and CD power. Full CD operation for 100 s with reactor-relevant high values of normalized beta and bootstrap current fraction (I-p = 2.4 MA, beta(N) = 4.3, f(BS) = 0.69, (n) over bar (e)/n(GW) = 0.86, H-H98y2 = 1.3) is expected in a highly-shaped low-aspect-ratio configuration (A = 2.65).

引用

页码：1512 / 1523

页数：12

共 34 条

[1] Density peaking, anomalous pinch, and collisionality in tokamak plasmas [J].