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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)Totsuka, Toshiyuki; Sakata, Shinya
JAEA-Technology 2009-006, 36 Pages, 2009/05
JAEA-Technology-2009-006.pdf:8.42MB
The functions of JT-60 discharge control computer system and the data processing computer system will be integrated into a new JT-60SA supervisory control system to improve the operational efficiency of the JT-60 control computer system. In this report, we first show the necessary requirements for the new JT-60SA supervisory control system that should have high cost performance and maintenability. Next, overall system image of the new JT-60SA supervisory control system is presented and the necessary functions and the issues to be solved in the development are shown. Finally, the necessary manpower for this development and performance of the computer hardware, and the expected reduction of maintenance cost of the computer system are described.
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.
Totsuka, Toshiyuki; Suzuki, Yoshio; Sakata, Shinya; Oshima, Takayuki; Iba, Katsuyuki*
Fusion Engineering and Design, 83(2-3), p.287 - 290, 2008/04
Times Cited Count：1 Percentile：10.5(Nuclear Science & Technology)no abstracts in English
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：24.35(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.
Suzuki, Yoshio; Nakajima, Kohei; Kushida, Noriyuki; Kino, Chiaki; Aoyagi, Tetsuo; Nakajima, Norihiro; Iba, Katsuyuki*; Hayashi, Nobuhiko; Ozeki, Takahisa; Totsuka, Toshiyuki; et al.
Fusion Engineering and Design, 83(2-3), p.511 - 515, 2008/04
Times Cited Count：3 Percentile：24.35(Nuclear Science & Technology)In collaboration with the Naka Fusion Institute of Japan Atomic Energy Agency (NFI/JAEA) and the National Institute for Fusion Science of National Institute of Natural Science (NIFS/NINS), Center for Computational Science and E-systems of Japan Atomic Energy Agency (CCSE/JAEA) aims at establishing an integrated framework for experiments and analyses in nuclear fusion research based on the Atomic Energy Grid InfraStructure (AEGIS). AEGIS has been being developed by CCSE/JAEA aiming at providing the infrastructure that enables atomic energy researchers in remote locations to carry out R&D efficiently and collaboratively through the Internet. Toward establishing the integrated framework, we have been applying AEGIS to pre-existing three systems.
Iba, Katsuyuki*; Ozeki, Takahisa; Totsuka, Toshiyuki; Suzuki, Yoshio; Oshima, Takayuki; Sakata, Shinya; Sato, Minoru; Suzuki, Mitsuhiro; Hamamatsu, Kiyotaka; Kiyono, Kimihiro
Fusion Engineering and Design, 83(2-3), p.495 - 497, 2008/04
Times Cited Count：4 Percentile：30.37(Nuclear Science & Technology)Fusion research grid is an environment of collaborative researches using a network that connects scientists far apart and let them collaborate effectively over the difference in time and distance in a nuclear fusion research. Fundamental technology of Fusion research grid has been developed at JAEA in the VizGrid project under the e-Japan project at Ministry of Education, Culture, Sports, Science and Technology (MEXT). Remote research environments of experiments, diagnostics, analyses and communications were developed on Fusion research grid. We have developed prototype systems that include a remote experiment system, a remote diagnostics system, and a remote analysis system. All users can access these systems from anywhere because Fusion research grid does not required closed network like Super SINet to maintain security. The prototype systems were verified in experiments at JT-60U and their availability was confirmed.
Oshima, Takayuki; Kiyono, Kimihiro; Sakata, Shinya; Sato, Minoru; Totsuka, Toshiyuki; Iba, Katsuyuki*; Ozeki, Takahisa; Hirayama, Toshio
Fusion Engineering and Design, 82(5-14), p.1210 - 1215, 2007/10
Times Cited Count：2 Percentile：19.17(Nuclear Science & Technology)In JT-60U the data processing system, providing the data acquisition, producing the diagnostic data base, and communicating with the JT-60U control system. The MSP-ISP was replaced by a new Inter-Shot Processor based on the UNIX-OS of a workstation (UNIX-ISP) in 2005. The performance of UNIX-ISP is 2 times as high as that of the MSP-ISP in a stand-alone test using the data conversion program of the CXRS data. Thus we can expect the reduction of the processing time by the optimization of the total sequence. For the remote experiment, we have developed a system called RMSVR with which we can set discharge parameters from the remote site, and thereby the consistency of input parameters is checked. The high security of the remote experiment system is established by the certification and the encrypted communication based on ITBL. A verification test between a university and JAEA Naka indicates that the system using the HTTPS protocol is suitable for the remote experiment.
Totsuka, Toshiyuki
JAEA-Technology 2007-034, 41 Pages, 2007/05
JAEA-Technology-2007-034.pdf:4.45MB
The Man-Machine Interfacing System for JT-60 remote experiment was developed using the Java language which doesn't depend to a computer. The purpose is construction of environment that can do participation of experiment on JT-60 via the network from an outside. This report deals with the technical devices in this development and the equipped functions.
Sakata, Shinya; Totsuka, Toshiyuki; Kiyono, Kimihiro; Oshima, Takayuki; Sato, Minoru; Ozeki, Takahisa
Fusion Engineering and Design, 81(15-17), p.1775 - 1778, 2006/07
Times Cited Count：9 Percentile：54.64(Nuclear Science & Technology)no abstracts in English
Yonekawa, Izuru; Kawamata, Yoichi; Totsuka, Toshiyuki; Akasaka, Hiromi; Sueoka, Michiharu; Yoshida, Hidetoshi
Fusion Engineering and Design, 71(1-4), p.11 - 15, 2004/06
Times Cited Count：5 Percentile：36.03(Nuclear Science & Technology)The JT-60 control system based on workstation and VME-bus system features with UNIX system has been successfully performed at JT-60U advanced plasma experiment. The various hardware modifications and the adoption of the advanced plasma control algorithms have been continued to the JT-60 control system since its upgrade in 1991. The ZENKEI, supervisory control system, has entirely remodeled from its original 16 bits minicomputer and CAMAC system to the combination of workstation and VME-bus system configuration with Ethernet communication network system. The plasma control system executes real-time plasma equilibrium control command calculation within 250msec control cycle time. Each plant control subsystems are also modified along with same design concept to the ZENKEI. Currently, the minor modifications of the control system have been considered to realize longer pulse of discharge experiments without major change of the JT-60 equipment. Nearly 60 seconds of pulse length up to Ip=2MA, Bt=2T, PNBI=10MW(
30sec) plasma experiments will start from October in 2003.
Takano, Shoji*; Totsuka, Toshiyuki; Yonekawa, Izuru
KEK Proceedings 2003-16 (CD-ROM), 4 Pages, 2004/02
no abstracts in English
Yonekawa, Izuru; Kawamata, Yoichi; Totsuka, Toshiyuki; Akasaka, Hiromi; Sueoka, Michiharu; Kurihara, Kenichi; Kimura, Toyoaki; JT-60U Team
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.521 - 529, 2002/09
Times Cited Count：5 Percentile：35.17(Nuclear Science & Technology)The present status of JT-60 control system is reported including its original design concept, the progress of the system and various modifications since JT-60 upgrade. This control system has features of a functionally distributed and hierarchical structure, using CAMAC interfaces at the beginning, which are replaced to versatile module Europe (VME)-bus interfaces later, and a protective interlock system composed of both software and hard-wired interlock logics. Plant monitoring and control are performed by efficient data communication through CAMAC highways and Ethernet with TCP/IP protocols. Sequential control of a plasma discharges are executed by a combination of a remodeled VME-bus system and a timing system. At real-time plasma control system and a human interface system have been continuously modified corresponding to the progress of JT-60 experiments.
Matsuda, Toshiaki; Totsuka, Toshiyuki; Tsugita, Tomonori; Oshima, Takayuki; Sakata, Shinya; Sato, Minoru; Iwasaki, Keita*
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.512 - 520, 2002/09
Times Cited Count：3 Percentile：23.88(Nuclear Science & Technology)no abstracts in English
Totsuka, Toshiyuki; Akasaka, Hiromi; Sueoka, Michiharu; Takano, Shoji*; Yonekawa, Izuru
Fusion Engineering and Design, 60(3), p.409 - 414, 2002/06
Times Cited Count：2 Percentile：17.42(Nuclear Science & Technology)no abstracts in English
Takano, Shoji*; Akasaka, Hiromi; Totsuka, Toshiyuki; Yonekawa, Izuru
NIFS-MEMO-36, p.443 - 446, 2002/06
no abstracts in English
Akasaka, Hiromi; Sueoka, Michiharu; Takano, Shoji*; Totsuka, Toshiyuki; Yonekawa, Izuru; Kurihara, Kenichi; Kimura, Toyoaki
JAERI-Tech 2001-087, 109 Pages, 2002/01
JAERI-Tech-2001-087.pdf:6.83MB
The JT-60 discharge control system had been used since the start of JT-60 experiment in 1985, was renewed in March, 2001. The new system consists of a UNIX workstation and a VME-bus system, and features a distributed control system. The workstation performs message communication with a VME-bus system and controllers of JT-60 sub-systems and data processing for discharge control. The VME-bus system performs discharge sequence control. The replacement has improved the control function and reliability of the discharge control system and also has provided sufficient performance necessary for future modifications of JT-60. The new system has been running successfully since April 2001. The data acquisition speed was confirmed to be twice faster than the previous one. This report describes major functions of the discharge control system, technical ideas for developing the system and results of the initial operation in detail.
Yonekawa, Izuru; Totsuka, Toshiyuki; Akasaka, Hiromi; Sueoka, Michiharu; Takano, Shoji*; Kurihara, Kenichi
Fusion Engineering and Design, 48(1-2), p.17 - 23, 2000/08
Times Cited Count：3 Percentile：26.81(Nuclear Science & Technology)no abstracts in English
Omori, Yoshikazu; Matsukawa, Makoto; Totsuka, Toshiyuki; Furukawa, Hiroshi*
KEK Proceedings 99-16, p.361 - 364, 1999/11
no abstracts in English
