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Featured researches published by H. Iguchi.
Nuclear Fusion | 2007
A. Fujisawa; T. Ido; A. Shimizu; S. Okamura; K. Matsuoka; H. Iguchi; Y. Hamada; H. Nakano; S. Ohshima; K. Itoh; K. Hoshino; K. Shinohara; Y. Miura; Y. Nagashima; S.-I. Itoh; Michael Shats; Hua Xia; J.Q. Dong; L.W. Yan; K.J. Zhao; G. D. Conway; U. Stroth; A. V. Melnikov; L. G. Eliseev; Sergey E. Lysenko; S. V. Perfilov; C. Hidalgo; G. R. Tynan; C. Holland; P. H. Diamond
The present status of experiments on zonal flows in magnetic confinement experiments is examined. The innovative use of traditional and modern diagnostics has revealed unambiguously the existence of zonal flows, their spatio-temporal characteristics, their relationship to turbulence and their effects on confinement. In particular, a number of observations have been accumulated on the oscillatory branch of zonal flows, named geodesic acoustic modes, suggesting the necessity for theories to give their proper description. In addition to these basic properties of zonal flows, several new methods have elucidated the processes of zonal flow generation from turbulence. Further investigation of the relationship between zonal flows and confinement is strongly encouraged as cross-device activity including low temperature, toroidal and linear devices.
Journal of Fusion Energy | 1996
M. Fujiwara; K. Yamazaki; M. Okamoto; J. Todoroki; T. Amano; T. Watanabe; T. Hayashi; Heiji Sanuki; Noriyoshi Nakajima; Kimitaka Itoh; H. Sugama; K. Ichiguchi; S. Murakami; O. Motojima; J. Yamamoto; T. Satow; N. Yanagi; S. Imagawa; K. Takahata; H. Tamura; A. Nishimura; A. Komori; N. Inoue; N. Noda; A. Sagara; Y. Kubota; N. Akaishi; S. Satoh; S. Tanahashi; H. Chikaraishi
The largest superconducting fusion machine, Large Helical Device (LHD), is now under construction in Japan and will begin operation in 1997. Design and construction of related R&D programs are now being carried out. The major radius of this machine is 3.9 m and the magnetic field on the plasma center is 3 T. The NbTi superconducting conductors are used in both helical coils and poloidal coils to produce this field. This will be upgraded in the second phase a using superfluid coil cooling technique. A negative ion source is being successfully developed for the NBI heating of LHD. This paper describes the present status and progress in its experimental planning and theoretical analysis on LHD, and the design and construction of LHD torus, heating, and diagnostics equipments.
Physics of Plasmas | 2000
A. Fujisawa; H. Iguchi; T. Minami; Y. Yoshimura; Kenji Tanaka; K. Itoh; H. Sanuki; S. Lee; M. Kojima; S.-I. Itoh; M. Yokoyama; S. Kado; S. Okamura; R. Akiyama; K. Ida; M. Isobe; S. Nishimura; M. Osakabe; I. Nomura; A. Shimizu; C. Takahashi; K. Toi; K. Matsuoka; Y. Hamada; M. Fujiwara
The bifurcation nature of the electrostatic structure is studied in the toroidal helical plasma of the Compact Helical System (CHS) [K. Matsuoka et al., Proceedings of the 12th International Conference on Plasma Physics and Controlled Nuclear Fusion Research, Nice, 1988 (International Atomic Energy Agency, Vienna, 1989), Vol. 2, p. 411]. Observation of bifurcation-related phenomena is introduced, such as characteristic patterns of discrete potential profiles, and various patterns of self-sustained oscillations termed electric pulsation. Some patterns of the electrostatic structure are found to be quite important for fusion application owing to their association with transport barrier formation. It is confirmed, as is shown in several tokamak experiments, that the thermal transport barrier is linked with electrostatic structure through the radial electric field shear that can reduce the fluctuation resulting in anomalous transport. This article describes in detail spatio-temporal evolution during self-sust...
Nuclear Fusion | 1999
S. Okamura; K. Matsuoka; R. Akiyama; D. S. Darrow; A. Ejiri; A. Fujisawa; M. Fujiwara; M. Goto; K. Ida; H. Idei; H. Iguchi; N. Inoue; M. Isobe; K. Itoh; S. Kado; K. Khlopenkov; T. Kondo; S. Kubo; A. Lazaros; S. Lee; G. Matsunaga; T. Minami; S. Morita; S. Murakami; Noriyoshi Nakajima; N. Nikai; S. Nishimura; I. Nomura; S. Ohdachi; K. Ohkuni
Variation of the plasma position relative to the centre of the helical coil winding is a very effective means of controlling the MHD stability and the trapped particle confinement in heliotron/torsatron systems, but improving one of these two characteristics with this parameter simultaneously has a detrimental effect on the other. The inward shifted configuration is favourable for drift orbit optimization but is predicted to be unstable according to the Mercier criterion. Various physics problems, such as electric field structure, plasma rotation and MHD phenomena, have been studied in the Compact Helical System (CHS) with a compromise intermediate position. With this standard configuration, CHS has yielded experimental results that contribute to the understanding of general toroidal confinement physics and low aspect ratio helical systems. In the recent experiments, it was found that a wide range of inward shifted configurations give stable plasma discharges without any restriction to the special pressure profile. Such an enhanced range of operation made it possible to study experimentally the drift orbit optimized configuration in heliotron/torsatron systems. The effect of configuration improvement was studied with plasmas in a low collisionality regime.
Nuclear Fusion | 1995
S. Okamura; K. Matsuoka; K. Nishimura; K. Tsumori; R. Akiyama; S. Sakakibara; H. Yamada; S. Morita; T. Morisaki; Noriyoshi Nakajima; Kenji Tanaka; J. Xu; K. Ida; H. Iguchi; A. Lazaros; T. Ozaki; Hideki Arimoto; A. Ejiri; M. Fujiwara; H. Idei; O. Kaneko; K. Kawahata; T. Kawamoto; A. Komori; S. Kubo; O. Motojima; V.D. Pustovitov; C. Takahashi; K. Toi; I. Yamada
High beta plasmas with a volume averaged equilibrium beta value of 2.1% were produced in CHS using tangential neutral beam injection. This beta value was achieved with the confinement improvement (reheat mode) observed after turning off strong gas puffing. Wall conditioning with titanium gettering was used to make high density operation (ne ? 8 ? 1019 m-3) possible for low magnetic fields (Bt = 0.6 T). The discharges start with the magnetic hill configuration (in vacuum) and finally achieve Mercier stable equilibrium owing to the self-stabilization effect given by the magnetic well which is produced by the plasma pressure. The Shafranov shift was about 40% of a plasma minor radius. Magnetic fluctuations did not increase with increasing plasma pressure when the beta value exceeded 1%. Dynamic poloidal field control was applied to suppress the outward plasma shift with increasing plasma pressure. Such operation gave an additional increase of beta value compared with the constant poloidal field operation
Nuclear Fusion | 1992
H. Yamada; K. Ida; H. Iguchi; S. Morita; O. Kaneko; Hideki Arimoto; M. Hosokawa; H. Idei; S. Kubo; K. Matsuoka; K. Nishimura; S. Okamura; Yasuhiko Takeiri; Y. Takita; C. Takahashi; K. Hanatani; H.C. Howe; S.P. Hirshman; D.K. Lee
The MHD equilibrium properties of neutral beam heated plasmas have been experimentally investigated in the Compact Helical System (CHS)-a low aspect ratio (Ap ~ 5) heliotron/torsatron. This configuration is characterized by a strong breaking of helical symmetry. The radial profiles measured by various diagnostics have shown a significant Shafranov shift due to the plasma pressure. The deviation of the magnetic axis from is vacuum position has become as large as 50% of the minor radius. When the three-dimensional equilibrium code VMEC is used to reconstruct the equilibrium from the experimental data, the result is in good agreement with the experimentally observed Shafranov shift as well as with the diamagnetic pressure in plasmas with β ≤ 1.2% and β0 ≤ 3.3%. This beta values corresponds to half of the conventional equilibrium β limit defined by the Shafranov shift reaching a value of half of the minor radius. Although tangential neutral beam injection causes pressure anisotropies, p||/p⊥ ≤ 3, the description of the equilibrium assuming isotropic pressure is consistent with the experiment
Review of Scientific Instruments | 1992
A. Fujisawa; H. Iguchi; M. Sasao; Y. Hamada; J. Fujita
Active control of beam trajectories using four sets of sweep plates is proposed for a heavy ion beam probe (HIBP) system on helical plasma, such as torsatron, stellarator, etc., in order to solve problems arising from the complicated beam trajectories in its nonaxisymmetrical magnetic field. By this method, a series of the probing beam trajectories giving a whole potential distribution can be managed to pass at a particular point (detector aperture) with the same angle. An equation is introduced as a guiding principle to simplify the optimization process of geometrical configuration of the HIBP system, which will be adjusted for different magnetic configurations by only changing the sweep plate voltages.
Review of Scientific Instruments | 1996
A. Fujisawa; H. Iguchi; S. Lee; T. P. Crowley; Y. Hamada; S. Hidekuma; M. Kojima
A 200 keV heavy ion beam probe (HIBP) on the compact helical system heliotron/torsatron uses a newly proposed method in order to control complicated beam trajectories in nonaxisymmetrical devices. As a result, the HIBP has successfully measured potential profiles of the toroidal helical plasma. This article will describe the results of the potential profile measurements, together with the HIBP system and procedures to realize the method.
Fusion Engineering and Design | 1997
K. Narihara; K. Yamauchi; I. Yamada; T. Minami; K. Adachi; A. Ejiri; Y. Hamada; K. Ida; H. Iguchi; K. Kawahata; T. Ozaki; K. Toi
Copyright (c) 1997 Elsevier Science S.A. All rights reserved. Thomson scattering systems diagnosing three regions of the large helical device (LHD) are presented. (1) An obliquely back-scattered Thomson scattering system gives full profiles of electron temperature (T e ) and density (n e ) along the major radius on the mid-plane with a spatial resolution of 1.5−4.0 cm. A piezo-actuated mirror is dynamically oriented so that the beams from ten 50 Hz repetition rate Nd:YAG lasers propagate a common path along a major radius, giving T e and n e profiles every 2 ms. (2) A cavity Thomson scattering system will measure two-dimensional T e and n e profiles along the laser beam propagating off-axially right and left in an optical cavity. This will diagnose the island structures in the outer edge region. (3) A fiber Thomson scattering system, in which laser light is guided by an optical fiber, is freely movable and conveniently used to probe the diverted plasma.
Physics of Plasmas | 2008
A. Fujisawa; K. Itoh; A. Shimizu; H. Nakano; S. Ohshima; H. Iguchi; K. Matsuoka; S. Okamura; T. Minami; Y. Yoshimura; K. Nagaoka; K. Ida; K. Toi; C. Takahashi; M. Kojima; S. Nishimura; M. Isobe; C. Suzuki; T. Akiyama; T. Ido; Y. Nagashima; S.-I. Itoh; P. H. Diamond
The experimental studies on zonal flows and turbulence have been carried out in Compact Helical System [K. Matsuoka, S. Kubo, M. Hosokawa et al., in Plasma Physics and Controlled Nuclear Fusion Research, Proc. 12th Int. Conf., Nice, 1988 (International Atomic Energy Agency, Vienna, 1989, Vol. 2, p. 411] using twin heavy ion beam probes. The paper presents the experimental observations of stationary zonal flow, nonlinear couplings between zonal flow and turbulence, and the role of zonal flow in the improved confinement, together with the recent discovery of zonal magnetic field. The presented experimental results strongly support the new paradigm that the plasma transport should be considered as a system of drift wave and zonal flows, and provides the first direct evidence for turbulence dynamo that the structured magnetic field can be really generated by turbulence.