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A Consideration on Increasing Current Density in Normal Conducting Toroidal Field Coil for Spherical Tokamak Power Plant

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plasma Science and Technology 2005年第2期7卷 2731-2733页

作者：宋云涛西尾敏 institute of plasma Physics Chinese Academy of Sciences Hefei 230031China department of fusion plasma research of japan atomic energy research institute naka-machi Naka-gunIbaraki-ken 311-0193Japan

The center post is the most critical component as an inboard part of the toroidal field coil for the low aspect ratio tokamak. During the discharge it endures not only a tremendous ohmic heating owing to its carrying a rather high current but also a large nuclear heating and irradiation owing to the plasma operation. All the severe operating conditions, including the structure stress intensity and the stability of the structure, largely limit the maximum allowable current density. But in order to contain a very high dense plasma, it is hoped that the fusion power plant system can operate with a much high maximum magnetic field BT ≥12 T-15 T in the center post. A new method is presented in this paper to improve the maximum magnetic field up to 17 T and to investigate the possibility of the normal conducting center post to be used in the future fusion tokamak power plant.

关键词： low aspect ratio tokamak power plant toroidal field coil center post high magnetic field

research on High Pressure Gas Injection As a Method of Fueling, Disruption Mitigation and plasma Termination for Future Tokamak Reactors

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plasma Science and Technology 2005年第5期7卷 3057-3061页

作者：宋云涛 S.Nishio institute of plasma Physics Chinese Academy of Sciences department of fusion plasma research of japan atomic energy research institutenaka-machi Naka-gun Ibaraki-ken 311-0193 Japan

High-pressure gas injection has proved to be an effective disruption mitigation tech- nique in DIII-D tokamak experiments. If the method can be applied in future tokamak reactors not only for disruption mitigation but also for plasma termination and fueling, it will have an attractive advantage over the pellet and liquid injection from the viewpoint of economy and engineering design. In order to investigate the feasibility of this option, a study has been carried out with relevant parameters for conveying tubes of different geometrical sizes and for different gases. These parameters include pressure drop, lagger time after the valve＇s opening, gas diffusion in an ultra-high vacuum condition, and particle number contour.

关键词： tokamak reactor disruption mitigation fueling gas injection

Anomalous Wave energy Deposition in the Beginning Phases of Wave Injection in JT-60U Lower Hybrid Current Drive Experiments

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Chinese Physics Letters 1999年第11期16卷 827-829页

作者： FANG Yu-de Kenkichi USHIGUSA Takashi KONDOH institute of plasma Physics Chinese Academy of SciencesHefei 230031 JT-60U Experiment Division Naka Fusion Research EstablishmentJapan Atomic Energy Research InstituteNaka-MachiNaka-gunIbaraki-kenJapan

An anomalous phenomenon of wave energy deposition and its evolution were noticed in the beginning phases of lower hybrid wave injection in JT-60U experiments. It was found that the driven currents are always formed in the central region of the plasma column in the first several hundred milliseconds of the wave pulses, no matter what N|| spectrum of the waves is. Then the driven current profile will change to their normal situation gradually, which depends on N|| spectrum closely.

关键词： wave spectrum Wave

A New Regime for Studying the High Bootstrap Current Fraction plasma

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Chinese Physics Letters 2001年第7期18卷 931-932页

作者： X.Gao A.Isayama Y.Kamada K.Ushigusa T.Fujita T.Suzuki japan atomic energy research institute Naka Fusion Research EstablishmentNaka-machiNaka-gunIbaraki-ken 311-01Japan institute of plasma Physics Chinese Academy of SciencesP.O.Box 1126Hefei 230031

A new experimental regime has recently been studied for achieving high fraction of the bootstrap current in the JT-60U hydrogen *** high poloidal beta(βp~3.61)plasma was obtained by high-power neutral beam injection heating at very high edge safety factor(Ip=0.3 MA,Bt=3.65 T,qeff=25-35)region,and the bootstrap current fraction(fBS)was about 40%using the ACCOME code *** was observed that there were no magnetohydrodynamics instabilities to retard the increase ofβp and fBS parameters in the new regime.

关键词： calculation. Bootstrap neutral

Development of the PARASOL Code and Full Particle Simulation of Tokamak plasma with an Open-Field SOL-Divertor Region Using PARASOL

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plasma Science and Technology 2011年第3期13卷 316-325页

作者： T. TAKIZUKA japan atomic energy Agency Naka Fusion Institute Naka 311-0193 Japan

The PARASOL code and the simulation by using PARASOL are introduced briefly. The PARASOL code with particle-in-cell （PIC） method and binary collision model was developed in JAERI and JAEA. Simulations using PARASOL code were carried out in order to investigate the power and particle control with diveror system in fusion reactors. The one-dimensional （1D） version of PARASOL was adopted to investigate the Bohm criterion, the supersonic flow, the SOL heat conduction, and so on. The heat propagation due to edge localized mode （ELM） was studied with the 1D-dynamic PARASOL. The two-dimensional version of PARASOL for the whole tokamak plasma including scrape-off-layer （SOL）-divertor region was useful for simulating the SOL flow pattern, the electric field formation etc. Based on PARASOL simulation results, improved physics modeling for the fluid simulation was built up.

关键词： tolkamak plasma scrape-off layer divertor sheath heat transport plasmaflow radial electric field particle simulation collision model

Overall Features of EAST Operation Space by Using Simple Core-SOL-Divertor Model

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plasma Science and Technology 2006年第1期8卷 114-117页

作者： R.HIWATARI A.HATAYAMA 朱思铮 T.TAKIZUKA Y.TOMITA Oentral research institute of Electric Power Industry TokyoJapan Faculty of Science and Technology Keio UniversityYokohamaJapan institute of plasma Physics Chinese Academy of SciencesHefei230031 China naka fusion energy Establishment Japan Atomic Energy Research InstituteIbarakiJapan National institute for fusion Science TokiJapan

A simple Core-SOL-Divertor （C-S-D） model has been developed to investigate qualitatively the overall features of the operational space for the integrated core and edge plasma. To construct the simple C-S-D model, a simple core plasma model of ITER physics guidelines and a two-point SOL-divertor model are used. The simple C-S-D model is applied to the study of the EAST operational space with lower hybrid current drive experiments under various kinds of trade-off for the basic plasma parameters. Effective methods for extending the operational space are also presented, From this study for the EAST operational space, it is evident that the C-S-D model is a useful tool for understanding qualitatively the overall features of the plasma operational space.

关键词： divertor modeling particle balance core-edge interface EAST

Dynamics of Secondary Large-Scale Structures in ETG Turbulence Simulations

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plasma Science and Technology 2006年第1期8卷 110-113页

作者：李继全 Y.KISHIMOTO 董家齐 N.MIYATO T.MATSUMOTO Southwestern institute of Physics and SWIP-DUT Joint Lab for Fusion Plasma PhysicsChengdu 610041China department of Fundamental energy Kyoto University611-0011 GokashoUjiJapan Naka Fusion Research EstablishmentJAERINakaIbaraki 311-0193Japan naka fusion research Establishment JAERINakaIbaraki 311-0193Japan

The dynamics of secondary large-scale structures in electron-temperature-gradient （ETG） turbulence is investigated based on gyrofluid simulations in sheared slab geometry. It is found that structural bifurcation to zonal flow dominated or streamer-like states depends on the spectral anisotropy of turbulent ETG fluctuation, which is governed by the magnetic shear. The turbulent electron transport is suppressed by enhanced zonal flows. However, it is still low even if the streamer is formed in ETG turbulence with strong shears. It is shown that the low transport may be related to the secondary excitation of poloidal long-wavelength mode due to the beat wave of the most unstable components or a modulation instability. This large-scale structure with a low frequency and a long wavelength may saturate, or at least contribute to the saturation of ETG fluctuations through a poloidal mode coupling. The result suggests a low fluctuation level in ETG turbulence.

关键词： large-scale structures ETG turbulence gyrofluid simulation tokamak

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

Modelling of Edge plasma on JT-60U Tokamak by Using SOLPS5.0 Code

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plasma Science and Technology 2011年第3期13卷 302-306页

作者：陈一平 H. KAWASHIMA N. ASAKURA K. SHIMIZU H. TAKENAGA institute of plasma Physics Chinese Academy of Sciences Hefei 230031 China japan atomic energy Agency Naka-shi Ibaraki-Ken 311-0193 Japan

The edge transport code SOLPS5.0 is used to model edge plasmas in the experi- mental shots on JT-60U and the profiles of the transverse particle and heat transport coefficients D, Xe and Xi along the outer midplane are obtained by fitting the simulational results to the experimental data in L-mode shot 39090 and H-mode shots 37851, 37856. The modelling and fitting results show that within the pedestal region in H-mode shots 37851 and 37856 the radial particle transport coefficient D exhibits a significant drop, but, for L-mode shot 39090, the obvious drop in both D and Xe was not found.

关键词： SOLPS5.0 JT-60U modelling