High-beta steady-state research and future directions on the Japan Atomic Energy Research Institute Tokamak-60 Upgrade and the Japan Atomic Energy Research Institute Fusion Torus-2 Modified

被引:22
作者
Ishida, S [1 ]
机构
[1] Japan Atom Energy Res Inst, Naka Fus Res Estab, Naka, Ibaraki 3100193, Japan
关键词
D O I
10.1063/1.1667487
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
In the Japan Atomic Energy Research Institute Tokamak-60 Upgrade (JT-60U), a high-beta(p) ELMy H-mode (high-poloidal-beta high-confinement-mode with edge localized mode) plasma was sustained with beta(N)similar to2.7 for 7.4 s. Real-time neoclassical tearing mode (NTM) stabilization system was established and effective NTM suppression by early electron cyclotron (EC) wave injection was demonstrated. High fusion triple product of n(i)(0)tau(E)T(i)(0)=3.1x10(20) keV.s.m(-3) was achieved using the negative-ion based neutral beam current drive with beta(N)similar to2.5 and the bootstrap current fraction f(BS)similar to50%. In a hot electron regime, a high electron cyclotron current drive efficiency of 4.2x10(18) A/W/m(2) was achieved at T(e)similar to21 keV. Innovative current start-up scenario produced a current hole plasma with a very high f(BS)similar to90%. No accumulation of helium and carbon impurities was observed for internal transport barrier (ITB) plasmas. While argon impurity was accumulated, EC injection effectively exhausted it across ITB. In a regime of ELM disappearance, a clear correlation between the ELM frequency and the toroidal velocity at pedestal was observed. In the Japan Atomic Energy Research Institute Fusion Torus-2 Modified (JFT-2M), high beta plasmas were produced with full ferritic inside wall up to beta(N)=3.3, where high recycling steady H-mode discharges were developed up to beta(N)H(89P)similar to6 at n(e)/n(GW)similar to0.7-1.0 with ITB. JT-60U started long pulse experiment in late 2003 and JFT-2M will conduct wall stabilization experiment in early 2004. The modification of JT-60 to a fully superconducting coil tokamak is regarded as the national centralized tokamak facility program to accomplish the high beta steady-state research in a collisionless regime. (C) 2004 American Institute of Physics.
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页码:2532 / 2542
页数:11
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