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Present Status of jt-60sa Project and Development of Heating Systems for jt-60sa

Plasma Science and Technology 2011年第3期13卷 367-375页

作者： yoshitaka ikeda jt-60sa team Japan Atomic Energy Agency 801-1 Mukoyama Naka Ibaraki 311-0193 Japan

Present status of the jt-60sa （jt-60 Super Advanced） project, implemented jointly by Europe and Japan since 2007, is described. The design of the main tokamak components was completed in late 2008, and all the scientific missions are preserved to contribute to ITER and DEMO reactors. The construction of the jt-60sa has begun with procurement activities for the superconducting magnet systems, vacuum vessel, in-vessel components and other components under the relevant procurement arrangements between the implementing agencies of JAEA （Japan Atomic Energy Agency） in Japan and Fusion for Energy in Europe. Designs and developments of the auxiliary heating systems for jt-60sa have been progressing at JAEA so as to provide the total injection power of 41 MW for 100 s.

关键词： jt-60sa ITER DEMO JAEA heating systems

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Results and Future Plan of jt-60U towards Steady-State Tokamak Reactor

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Plasma Science and Technology 2004年第1期6卷 2151-2158页

作者： S.sakurai the jt-60 team Japan Atomic Energy Research Institute Naka Ibaraki 311-0193 JapanJapan Atomic Energy Research Institute Naka Ibaraki 311-0193 Japan

Recent results of jt-60U towards establishment of physics basis for ITER andadvanced tokamak operation are presented. Progress in high integrated performance is achieved withimprovement of N-NB and ECRF heating systems. In the next experimental campaign 2003～2004,discharge duration with 17 MW heating will be extended up to 30s for sustaining high-beta plasmalonger than the current diffusion time. Superconducting modification of jt-60 is planned todemonstrate high-beta plasma sustainment exceeding ideal MHD instability limit without wallstabilization.

关键词： jt-60U confinement study steady-state operation high confinement plasma plan and future plan

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Simulation Study on the ITB Formation during LHCD in jt-60U

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Plasma Science and Technology 2002年第2期4卷 1197-1206页

作者：崔正英 Osamu Naito Takeshi Fukudai Hiroshi Shirai yoshitaka ikeda Kenkichi Ushigusa Southwestern Institute of Physics Chengdu 610041 China Japan Atomic Energy Research Institute Naka Fusion Research Establishment Mukouyama 801-1 Naka-machi Naka-gun Ibaraki-ken 311-0193 Japan

A transport simulation has been done by using a i.5D time dependent transportcode to reproduce a formation of the ITB on electron temperature Profile during the long pu1seLHCD in jt-60U tokamak. The transport coefficients were assumed to reduce with a reversedmagnetic shear and the LH driven current profile was evaluated by fitting dynamic change inthe measured current profile. The gradual increase in the central electron temperature could beexplained by the change in the current profile during LHCD in the present simulation model. Theestimated LH-driven current profile by the transport code analysis shows a finite current densityat the plasma center. Analysis of transport simulation suggests some mechanisms for broadeningthe LH-driven current profile at the central region of the plasma.

关键词： LHCD Simulation Study on the ITB Formation during LHCD in jt-60U ITB

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