Oshima, Takayuki; Kiyono, Kimihiro; Sakata, Shinya; Sato, Minoru; Kominato, Toshiharu; Ozeki, Takahisa
Fusion Engineering and Design, 83(2-3), p.330 - 333, 2008/04
We have developed a prototype of new mass data acquisition system (P-MDAS) that can perform a faster data acquisition. This system is based on a general-purpose PXI (Compact PCI) bus standard. In 2004, standalone vivifications on the performance of P-MDAS were carried out (8- channel ADC, hard disk streaming). In 2005 and 2006, we examined its performance under the following environments: under remote diagnostic control using optical communication interface, under multiple controller PCs, under multiple PXI boards to increase the number of channels, under a long duration of data acquisition (45 seconds) with a high sampling rate (1 MHz) and a high resolution (14 bit). At the same time, we developed a MDAS server (UNIX WS) and verified its performance on the data transfer to Inter-Shot Processor. We are planning to increase the number of channels and conduct a performance verification of overall data processing system (DPS) with 10 GB/Shot of data acquisition.
Miyo, Yasuhiko; Yagyu, Junichi; Nishiyama, Tomokazu; Honda, Masao; Ichige, Hisashi; Kaminaga, Atsushi; Sasajima, Tadayuki; Arai, Takashi; Sakasai, Akira
Fusion Engineering and Design, 83(2-3), p.337 - 340, 2008/04
no abstracts in English
Okano, Fuminori; Shinozaki, Shinichi; Honda, Atsushi; Oshima, Katsumi; Numazawa, Susumu*; Ikeda, Yoshitaka
Fusion Engineering and Design, 83(2-3), p.280 - 282, 2008/04
no abstracts in English
Honda, Atsushi; Okano, Fuminori; Oshima, Katsumi; Akino, Noboru; Kikuchi, Katsumi; Tanai, Yutaka; Takenouchi, Tadashi; Numazawa, Susumu*; Ikeda, Yoshitaka
Fusion Engineering and Design, 83(2-3), p.276 - 279, 2008/04
The control system of the cryogenic facility in the JT-60 NBI system has been renewed by employing the PLC (Programmable Logic Controller) and SCADA (Supervisory Control And Data Acquisition) system. The original control system was constructed about 20 years ago by specifying the DCS (Distributed Control System) computer to deal with 400 feedback loops. Recently, troubles on this control system have increased due to its aged deterioration. To maintain a high reliability of the cryogenic facility, a new control system has been intended with PLC and SCADA system. By optimizing the function blocks and connecting them in the FBD language, the feedback loops in the new control system have been successfully replaced from DCS to PLC without software developer. At present, the new control system has worked well. This is the first application of the marketable PLC to the actual system with feedback loops of 400 produced by the user itself.
Sueoka, Michiharu; Totsuka, Toshiyuki; Kawamata, Yoichi; Kurihara, Kenichi; Seki, Akiyuki
Fusion Engineering and Design, 83(2-3), p.283 - 286, 2008/04
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
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
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.
Sato, Minoru; Kiyono, Kimihiro; Oshima, Takayuki; Sakata, Shinya; Konoshima, Shigeru; Ozeki, Takahisa
Fusion Engineering and Design, 83(2-3), p.334 - 336, 2008/04
JT-60U's diagnostic systems have been using CAMAC systems for their control and data acquisition. But the transient recorders used to store the diagnostic data are rather old and lack in memory expansion. Therefore, for a long pulse discharge of more than 15 seconds, data sampling rate must be reduced to cover the whole discharge period. The acquired data has, however, low time resolution and is sometimes insufficient for detailed analysis. To solve this problem, the transient recorders should be replaced with those having larger memory, but without modification to the existing data processing infrastructure. For this purpose, we have developed a new data acquisition system with SPARC CPU on VMEbus and the associated software, to retain the functionality of CAMAC control. We have applied this system to the existing bolometric diagnostics. In this paper, detail of design will be described.
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
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.
Tokuda, Shinji; Okubo, Hiroshi*; Fujisaki, Masahide*; Karube, Yukihiro*
no journal, ,
An MHD (MagnetoHydroDynamic) stability code MARG2D has recently been developed which identifies the stability against ideal MHD perturbations in a tokamak. The code reduces the stability problem to an eigenvalue problem and solves the problem less than ten seconds when a massively parallel computer (SGI Altix 3700Bx2) is used. Real time stability analysis therefore becomes probable since the characteristic time is seconds for changing the pressure profile in ITER. To this end we are now developing by using FPGA (Field Programmable Gate Array) a special purpose computer that solves the eigenvalue problem. We report on the progress of this project, especially on matrix operations by FPGA with the study of performance.