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plasma operationTamai, Hiroshi; Akiba, Masato; Azechi, Hiroshi*; Fujita, Takaaki; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; Hosogane, Nobuyuki; Ichimura, Makoto*; et al.
Nuclear Fusion, 45(12), p.1676 - 1683, 2005/12
Times Cited Count：15 Percentile：45.44(Physics, Fluids & Plasmas)Design studies are shown on the National Centralized Tokamak facility. The machine design is carried out to investigate the capability for the flexibility in aspect ratio and shape controllability for the demonstration of the high-beta steady state operation with nation-wide collaboration, in parallel with ITER towards DEMO. Two designs are proposed and assessed with respect to the physics requirements such as confinement, stability, current drive, divertor, and energetic particle confinement. The operation range in the aspect ratio and the plasma shape is widely enhanced in consistent with the sufficient divertor pumping. Evaluations of the plasma performance towards the determination of machine design are presented.
Kishimoto, Hiroshi; Ishida, Shinichi; Kikuchi, Mitsuru; Ninomiya, Hiromasa
Nuclear Fusion, 45(8), p.986 - 1023, 2005/08
Times Cited Count：40 Percentile：28.81(Physics, Fluids & Plasmas)The Japanese large tokamak JT-60 has been focusing its research emphases to develop a high performance plasma, namely high confinement, high temperature and high density, and to sustain it non-inductively for a long time with possible minimization of external power input. The first demonstration of high bootstrap current discharges in a high-poloidal-beta mode (high-p) and the concept development of a steady-state tokamak reactor SSTR based on this experimental achievement initiated the so-called "advanced tokamak research". The first observation of internal transport barriers in the JT-60 high-p mode was followed by the world-wide explorations of reversed shear discharges associated with internal transport barriers. The advanced tokamak research is now the major trend of the current tokamak development. A new concept of compact ITER was developed and proposed in the context of this advanced tokamak approach pursued on JT-60.
Kajiwara, Ken*; Ikeda, Yoshitaka; Seki, Masami; Moriyama, Shinichi; Oikawa, Toshihiro; Fujii, Tsuneyuki; JT-60 Team
Nuclear Fusion, 45(7), p.694 - 705, 2005/07
Times Cited Count：60 Percentile：85.7(Physics, Fluids & Plasmas)Electron cyclotron heating (ECH) assisted start-up experiment was performed in JT-60U. The breakdown loop voltage, becoming the maximum value at the plasma start-up, successfully reduced from 30 V to 4 V (E = 0.26 V/m) by 200 kW ECH. This fulfills the value less than 0.3 V/m, which corresponds to the maximum electric field required in ITER. Moreover, in order to investigate properties of start-up plasmas, parameter scans of the ECH power, prefilled gas pressure, resonant position, polarization angle and injection position were carried out and the dependence on them were obtained. It was revealed that the properties have dependences on the injection position and polarization angle in large tokamaks although they seemed to have no dependence on them from the experiments in small and medium tokamaks. In addition, in experiments of the plasma start-up using second and third harmonic ECH, it was found that the plasma current was ramped by 800 kW second harmonic ECH and was not ramped by 1.6 MW third harmonic ECH even with 7 MW neutral beam injection heating.
Ikeda, Yoshitaka; Kubo, Shin*
Purazuma, Kaku Yugo Gakkai-Shi, 81(3), p.160 - 166, 2005/03
The local profile controls of electron temperature and current in fusion-oriented devices using the electron cyclotron (EC) wave is reviewed. Recent progress of the EC heating system that enabled those controls is briefly described. The specific feature of EC wave heating is local and high power density heating properties. Current drive and electron temperature profile control experiments using EC wave performed in order to improve and investigate plasma confinement properties are discussed.
Inoue, Takashi; Sakamoto, Keishi
Nihon Genshiryoku Gakkai-Shi, 47(2), p.120 - 127, 2005/02
no abstracts in English
Miura, Yukitoshi; Hoshino, Katsumichi; Kusama, Yoshinori
Purazuma, Kaku Yugo Gakkai-Shi, 80(8), p.653 - 661, 2004/08
A series of experimental program on the JAERI Fusion Torus-2M (JFT-2M) was completed in March, 2004. In the experimental operation for 21 years since the first plasma on April 27, 1983, many significant results leading the fusion energy research and plasma physics have been produced in researches on high confinement mode (H-mode), heating and current drive, advanced plasma control, compatibility of low activation ferritic steel with improved confinement mode, etc. Among these results, some important results are presented.
Tamai, Hiroshi; Kurita, Genichi; Matsukawa, Makoto; Urata, Kazuhiro*; Sakurai, Shinji; Tsuchiya, Katsuhiko; Morioka, Atsuhiko; Miura, Yushi; Kizu, Kaname; Kamada, Yutaka; et al.
Plasma Science and Technology, 6(3), p.2281 - 2285, 2004/06
Times Cited Count：0 Percentile：0.02(Physics, Fluids & Plasmas)High performance steady-state operation for JT-60SC are evaluated by the TOPICS analysis. 
5 and bootstrap current fraction 86% is kept steady at I
=1.5 MA, B
=2 T by neutral beam power of 11 MW. The ERATO-J analysis shows that the external-kink mode with multiple toroidal mode numbers of n=1 and n=2 is stable at 
5.5 at the average ratio of conducting wall radius to plasma minor radius of about 1.2 with the wall stabilisation effect. Resistive wall modes, induced by a close location of the wall to plasma, is expected to be suppressed by the active feedback stabilisation with a set of non-axisymmetric field coils behind the stabilising plates. Further optimisation for the high- accessibility by the plasma shaping is performed with the TOSCA analysis. The plasma shaping factor defined as S=(I/aB)q
and strongly correlated to the plasma elongation and triangularity, is scanned from 4 to 6, which extends the availability of current and pressure profile control for the high performance plasma operation.
Inoue, Takashi; Hanada, Masaya; Iga, Takashi*; Imai, Tsuyoshi; Kashiwagi, Mieko; Kawai, Mikito; Morishita, Takatoshi; Taniguchi, Masaki; Umeda, Naotaka; Watanabe, Kazuhiro; et al.
Fusion Engineering and Design, 66-68, p.597 - 602, 2003/09
Times Cited Count：21 Percentile：78.43(Nuclear Science & Technology)The neutral beam (NB) injection has been one of the most promising methods for plasma heating and current drive in tokamak fusion devices. JAERI has developed high energy electrostatic accelerators for the NB systems in JT-60U and ITER. Recent progress on this R&D are as follows: 1) In the JT-60U NB system, some of the beams has been deflected due to distorted electric field in the accelerator, resulting in an excess heat load on the NB port. By correcting the electric field, a continuous injection of H
beam was succeeded for 10 s with the NB power of 2.6 MW at 355 keV. 2) To increase the beam energy, a metal structure called stress ring was designed. The ring reduces electric field concentration at the triple junction point (interface between metal and dielectric insulator inside vacuum). Initial test of the accelerators with the stress rings has shown higher voltage hold off performance in both accelerators for JT-60U and ITER R&D than that without rings.
Inoue, Takashi
Purazuma, Kaku Yugo Gakkai-Shi, 78(5), p.398 - 404, 2002/05
Neutral beam (NB) heating and current drivesystem for ITER fires the energetic particle beams of 1 MeV, 33 MW (16.5 MW/NB injector) into the fusion plasma. The design allows late installation of third NB injector for upgrade in current drive experiment toward steady state operation. The ITER NB system has been designed to fulfill requirements of the plasma physics, including advanced scenario achieved with off-axis current drive by NB. A design overview of the ITER NB system is described. The paper also reports recent R&D status of ion source and accelerator, as key components of the NB system, toward ITER construction. NB heating and current drive performance required in future tokamak reactors are discussed together with the necessary R&D issues.
Inoue, Takashi; Di Pietro, E.*; Hanada, Masaya; Hemsworth, R. S.*; Krylov, A.*; Kulygin, V.*; Massmann, P.*; Mondino, P. L.*; Okumura, Yoshikazu; Panasenkov, A.*; et al.
Fusion Engineering and Design, 56-57, p.517 - 521, 2001/10
Times Cited Count：64 Percentile：96.58(Nuclear Science & Technology)no abstracts in English
Inoue, Takashi; Hemsworth, R. S.*; Kulygin, V.*; Okumura, Yoshikazu
Fusion Engineering and Design, 55(2-3), p.291 - 301, 2001/07
Times Cited Count：25 Percentile：84.31(Nuclear Science & Technology)no abstracts in English
Inoue, Takashi; Di Pietro, E.*; Mondino, P. L.*; Bayetti, P.*; Hemsworth, R. S.*; Massmann, P.*; Fujiwara, Yukio; Hanada, Masaya; Miyamoto, Kenji; Okumura, Yoshikazu; et al.
Review of Scientific Instruments, 71(2), p.744 - 746, 2000/02
Times Cited Count：17 Percentile：67.86(Instruments & Instrumentation)no abstracts in English
Polevoi, A. R.; Nishio, Satoshi; Ushigusa, Kenkichi
JAERI-Tech 2000-001, p.16 - 0, 2000/01
JAERI-Tech-2000-001.pdf:0.85MB
no abstracts in English
Yoshino, Ryuji
Purazuma, Kaku Yugo Gakkai-Shi, 75(12), p.1337 - 1374, 1999/12
no abstracts in English
*; Takizuka, Tomonori; Hatayama, Akiyoshi*; *
Journal of Nuclear Materials, 266-269, p.526 - 531, 1999/00
Times Cited Count：3 Percentile：28.64(Materials Science, Multidisciplinary)no abstracts in English
*; Takizuka, Tomonori; Hatayama, Akiyoshi*; *
Journal of the Physical Society of Japan, 66(12), p.3815 - 3825, 1997/12
Times Cited Count：5 Percentile：47.57(Physics, Multidisciplinary)no abstracts in English
Yoshino, Ryuji; Nakamura, Yukiharu; Neyatani, Yuzuru
Nuclear Fusion, 37(8), p.1161 - 1166, 1997/00
Times Cited Count：8 Percentile：30.8(Physics, Fluids & Plasmas)no abstracts in English
Senda, Ikuo*; Shoji, Teruaki; Tsunematsu, Toshihide; *; Fujieda, Hirobumi*
Nuclear Fusion, 37(8), p.1129 - 1145, 1997/00
Times Cited Count：9 Percentile：33.74(Physics, Fluids & Plasmas)no abstracts in English
Yoshino, Ryuji; JT-60 Team
Proc. of 36th IEEE Conf. on Decision and Control, 4, p.3709 - 3714, 1997/00
no abstracts in English
Koizumi, Koichi; Yamazaki, Kozo*
Purazuma, Kaku Yugo Gakkai-Shi, 72(12), p.1352 - 1361, 1996/12
no abstracts in English
