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Ferro, A.*; Gaio, E.*; Novello, L.*; Matsukawa, Makoto; Shimada, Katsuhiro; Kawamata, Yoichi; Takechi, Manabu
Fusion Engineering and Design, 98-99, p.1053 - 1057, 2015/10
Times Cited Count：3 Percentile：25.85(Nuclear Science & Technology)Takechi, Manabu; Matsunaga, Go; Sakurai, Shinji; Sasajima, Tadayuki; Yagyu, Junichi; Hoshi, Ryo*; Kawamata, Yoichi; Kurihara, Kenichi; JT-60SA Team; Nishikawa, T.*; et al.
Fusion Engineering and Design, 96-97, p.985 - 988, 2015/10
Times Cited Count：10 Percentile：64.63(Nuclear Science & Technology)Nakamura, Kazuo*; Jiang, Y.*; Liu, X.*; Mitarai, Osamu*; Kurihara, Kenichi; Kawamata, Yoichi; Sueoka, Michiharu; Hasegawa, Makoto*; Tokunaga, Kazutoshi*; Zushi, Hideki*; et al.
Fusion Engineering and Design, 86(6-8), p.1080 - 1084, 2011/10
Times Cited Count：4 Percentile：32.59(Nuclear Science & Technology)Sakata, Shinya; Yamaguchi, Taiji; Sugimura, Toru; Kominato, Toshiharu; Kawamata, Yoichi; Totsuka, Toshiyuki; Sato, Minoru; Sueoka, Michiharu; Naito, Osamu
Fusion Science and Technology, 60(2), p.496 - 500, 2011/08
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)For a steady state operation of JT-60SA, a plasma feedback control using various diagnostic sensor signals plays an essential role. To realize this, Real Time Diagnostic Signals acquisition System, RTDS, which utilizes PC-based real-time OS "INtime", has been under consideration toward JT-60SA project. Moreover, long-time experiments more than 100 seconds will be planned in JT-60SA project. Therefore, real time monitoring will be required as an essential function that displays acquired diagnostic signals on real time during long-time experiment. This function will be also realized by utilizing RTDS.
Kawamata, Yoichi; Sugimura, Toru; Yamaguchi, Taiji; Sueoka, Michiharu; Sakata, Shinya; Totsuka, Toshiyuki; Sato, Minoru; Kominato, Toshiharu; Naito, Osamu
Fusion Science and Technology, 60(2), p.491 - 495, 2011/08
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Yoshida, Maiko; Sakamoto, Yoshiteru; Sueoka, Michiharu; Kawamata, Yoichi; Oyama, Naoyuki; Suzuki, Takahiro; Kamada, Yutaka; JT-60 Team
Fusion Engineering and Design, 84(12), p.2206 - 2213, 2009/12
Times Cited Count：17 Percentile：72.88(Nuclear Science & Technology)A fast charge exchange recombination spectroscopy (CXRS) system has been developed for the real-time measurement and feedback control of ion temperature (
) profile and toroidal rotation velocity (
) in JT-60U. In order to control and in real-time, the charge exchange recombination spectroscopy with high time resolution, the real-time processor system, and the real-time control system have been developed. Utilizing this system, real-time control of the gradient has been demonstrated with neutral beams at high beta plasmas. The strength of the internal transport barrier is controlled. Moreover, the real-time control of has been demonstrated from counter (anti parallel to the plasma current, 
) to co (parallel to the ) direction.
Sakata, Shinya; Kiyono, Kimihiro; Sato, Minoru; Kominato, Toshiharu; Sueoka, Michiharu; Hosoyama, Hiroki; Kawamata, Yoichi
Fusion Engineering and Design, 84(7-11), p.1680 - 1683, 2009/06
Times Cited Count：1 Percentile：10.22(Nuclear Science & Technology)no abstracts in English
Kurihara, Kenichi; Kawamata, Yoichi; Sueoka, Michiharu; Wang, F.*; Nakamura, Kazuo*; Mitarai, Osamu*; Sato, Konosuke*; Zushi, Hideki*; Hanada, Kazuaki*; Sakamoto, Mizuki*; et al.
Kyushu Daigaku Oyo Rikigaku Kenkyujo RIAM Foramu 2008 Koen Yoshi, p.66 - 69, 2008/06
no abstracts in English
Sueoka, Michiharu; Totsuka, Toshiyuki; Kawamata, Yoichi; Kurihara, Kenichi; Seki, Akiyuki
Fusion Engineering and Design, 83(2-3), p.283 - 286, 2008/04
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)For safety and efficient operation of a fusion device, appropriate information should be provided to the personnel related to experiment. In order to realize this, we have newly developed highlight screens displaying the plasma movie, the status of discharge sequence, the discharge schedule, the present status of trouble, etc., with the large (65 inch) monitor TV in front of the central consoles. These highlight screens are automatically switched according to the timing signal of JT-60 discharge sequence and/or the operator's request. We call this system the supervisory discharge operation monitoring system. This report deals with the technical details of this system including the plasma movie database system and the discharge information management system.
Kawamata, Yoichi; Naito, Osamu; Kiyono, Kimihiro; Itami, Kiyoshi; Totsuka, Toshiyuki; Akasaka, Hiromi; Sueoka, Michiharu; Sato, Tomoki; Oshima, Takayuki; Sakata, Shinya; et al.
Fusion Engineering and Design, 83(2-3), p.198 - 201, 2008/04
Times Cited Count：3 Percentile：23.55(Nuclear Science & Technology)The design activity of JT-60SA (JT-60 Super Advanced) which is remodeled to a superconducting tokamak device has been starting under the JA-EU collaborative ITER-BA project. For the JT-60SA control system, the existing system should be reused as much as possible from the viewpoint of cost-effectiveness. We have just begun to discuss the configuration of the advanced Supervisory Control System (SVCS) including the following systems: (1) ultimately flexible real-time control system, (2) precise timing system enough to clarify cause and effect, and (3) safety shutdown control system. In this report, we present the design study of the JT-60SA SVCS with focusing on these systems.
Sueoka, Michiharu; Kawamata, Yoichi; Kurihara, Kenichi; Seki, Akiyuki
JAEA-Technology 2008-021, 23 Pages, 2008/03
JAEA-Technology-2008-021.pdf:10.47MB
A plasma movie is generally expected as one of the most efficient methods to know what plasma discharge has been conducted in the experiment. The JT-60 plasma movie is composed of video camera picture looking at a plasma, computer graphics (CG) picture, and magnetic probe signal as a sound channel. In order to use this movie efficiently, we have developed a new system having the following functions: (a) To store a plasma movie in the movie database system automatically combined with the plasma shape CG and the sound according to a discharge sequence. (b) To make a plasma movie is available (downloadable) for experiment data analyses at the Web-site. Especially, this system aimed at minimizing the development cost, and it tried to develop the real-time plasma shape visualization system (RVS) without any operating system (OS) customized for real-time use. As a result, this system succeeded in working under Windows XP. This report deals with the technical details of the plasma movie database system and the real-time plasma shape visualization system.
Takenaga, Hidenobu; Kubo, Hirotaka; Sueoka, Michiharu; Kawamata, Yoichi; Yoshida, Maiko; Kobayashi, Shinji*; Sakamoto, Yoshiteru; Iio, Shunji*; Shimomura, Koji*; Ichige, Hisashi; et al.
Nuclear Fusion, 48(3), p.035011_1 - 035011_6, 2008/03
Times Cited Count：3 Percentile：13.2(Physics, Fluids & Plasmas)A burning plasma simulation scheme has been developed with consideration for temperature dependence of the DT fusion reaction rate in JT-60U. The heating power for the simulation of alpha particle heating was calculated using real-time measurements of density and ion temperature. Response of a simulated fusion gain to the density was investigated in this scheme with constant heating power for the simulation of external heating, in order to understand burn controllability by the fuel density in a fusion reactor. When temperature dependence of the fusion reaction rate was assumed as square of ion temperature, density dependence of the simulated fusion gain stronger than square of density was observed. Transport analysis using a 1.5 dimension transport code indicated that the strong density dependence is induced due to both change in a confinement improvement factor and change in a pressure profile.
Sueoka, Michiharu; Kawamata, Yoichi; Kurihara, Kenichi; Seki, Akiyuki
Fusion Engineering and Design, 82(5-14), p.1008 - 1014, 2007/10
Times Cited Count：2 Percentile：18.73(Nuclear Science & Technology)A plasma movie is generally expected as one of the most efficient methods to know what plasma discharge has been conducted in the experiment. On this motivation we have developed and operated a real-time plasma shape visualization system over ten years. The current plasma movie is composed of (1) video camera picture looking at a plasma, (2) computer graphic (CG) picture, and (3) magnetic probe signal as a sound channel. In order to use this movie efficiently, we have developed a new plasma movie database system, where a plasma movie is available (downloadable) for experiment data analyses at the Web-site. This new system and its future prospects will be discussed in detals from a technological point of view.
Shimomura, Koji*; Takenaga, Hidenobu; Tsutsui, Hiroaki*; Mimata, Hideyuki*; Iio, Shunji*; Miura, Yukitoshi; Tani, Keiji; Kubo, Hirotaka; Sakamoto, Yoshiteru; Hiratsuka, Hajime; et al.
Fusion Engineering and Design, 82(5-14), p.953 - 960, 2007/10
Times Cited Count：3 Percentile：25.51(Nuclear Science & Technology)no abstracts in English
Yagyu, Junichi; Sasajima, Tadayuki; Miyo, Yasuhiko; Sakakibara, Satoru*; Kawamata, Yoichi
JAEA-Technology 2007-015, 27 Pages, 2007/03
JAEA-Technology-2007-015.pdf:2.94MB
The feedback control of the plasma position and shape based on signals of magnetic probes is performed on JT-60. The fabrication cost of these magnetic probes is very high. Therefore, the cost reduction is required for the use in a next device. On the other hand, the magnetic field measurement in three axial directions with the advanced technology (AT) probes is simultaneously made on LHD of NIFS. The AT-probe has been developed at a low fabrication cost and in compact size and light weight. The possibility of application of the AT-probe in a Tokamak device (JT-60U) has been investigated in collaboration between JAEA and NIFS. We designed and fabricated the casing and interface for the AT-probe, and installed it under the first wall of JT-60U. A comparison of output signals between the installed AT-probe and a existing magnetic probe was made. Tests have been carried out to evaluate the vibration resistance and the radioactive resistance through about two thousand shots with high performance plasmas including one hundred disruption shots in JT-60U. As a result, the AT-probe has a good performance and an enough usable prospect in environment of the Tokamak device.
Akasaka, Hiromi; Takano, Shoji; Sato, Tomoki; Kawamata, Yoichi
Heisei-18-Nendo Nagoya Daigaku Sogo Gijutsu Kenkyukai Kairo, Keisoku, Seigyo Gijutsu Kenkyukai Hokokushu, p.106 - 109, 2007/03
no abstracts in English
Yonekawa, Izuru; Sueoka, Michiharu; Hosoyama, Hiroki*; Kawamata, Yoichi; Suzuki, Takahiro; Kurihara, Kenichi
Fusion Engineering and Design, 81(15-17), p.1897 - 1903, 2006/07
Times Cited Count：2 Percentile：17.18(Nuclear Science & Technology)Recent years, plasma current profile (j-profile) control has been newly proposed to avoid instabilities in the high normalized-beta plasma. In particular, for the real-time profile feedback control, the control period should be roughly less than several tens of ms, including data communication among relating systems. In order to minimize data transfer time,the profile data being a function of time and position is required to decrease its data size for efficient data handling. A profile data,defined as 3-dimension time series data (q,R,Z,t), was reduced by introducing normalized minor radius rho in place of (R,Z). Data handling for profile control will be presented with their technical issues, together with computing hardware engineering.
Kurihara, Kenichi; Yonekawa, Izuru; Kawamata, Yoichi; Sueoka, Michiharu; Hosoyama, Hiroki*; Sakata, Shinya; Oshima, Takayuki; Sato, Minoru; Kiyono, Kimihiro; Ozeki, Takahisa
Fusion Engineering and Design, 81(15-17), p.1729 - 1734, 2006/07
Times Cited Count：13 Percentile：65.83(Nuclear Science & Technology)A large tokamak fusion device JT-60 is expected to explore more advanced tokamak discharge scenario towards the ITER and a future power reactor. We believe the following experimental issues are expected to be solved in JT-60. To clarify how to keep a steady-state plasma with high performance, and how to avoid plasma instabilities almost completely. By stimulus of this motivation, several essential development and modifications of plasma control and data acquisition systems have been performed in JT-60. In this report, we discuss the developments to improve the JT-60 plasma control and data acquisition systems. In addition, a future plasma control and data acquisition systems leading to a standard design for a power reactor is envisaged on the basis of the 20-year plasma operation experiences.
Takenaga, Hidenobu; Miura, Yukitoshi; Kubo, Hirotaka; Sakamoto, Yoshiteru; Hiratsuka, Hajime; Ichige, Hisashi; Yonekawa, Izuru*; Kawamata, Yoichi; Iio, Shunji*; Sakamoto, Ryuichi*; et al.
Fusion Science and Technology, 50(1), p.76 - 83, 2006/07
Times Cited Count：4 Percentile：30.68(Nuclear Science & Technology)no abstracts in English
Wang, F.*; Nakamura, Kazuo*; Mitarai, Osamu*; Kurihara, Kenichi; Kawamata, Yoichi; Sueoka, Michiharu; Sato, Konosuke*; Zushi, Hideki*; Hanada, Kazuaki*; Sakamoto, Mizuki*; et al.
Kyushu Daigaku Oyo Rikigaku Kenkyujo RIAM Foramu 2006 Koen Yoshi, p.138 - 141, 2006/06
no abstracts in English
