| Paper |
Title |
Page |
| TUP057 |
FPGA Digital Timing System for Fusion Plasma Diagnostics in LHD
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212 |
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- H. Nakanishi, S. Imazu, Y. Ito, K. Kawahata, M. Kojima, Y. Nagayama, M. Nonomura, M. Ohsuna, S. Sudo
NIFS, Gifu
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Funding: This work is performed with the support and under the auspices of the NIFS Collaborative Research Program NIFS09ULHH503.
The digital timing system for LHD diagnostics was developed more than ten years ago as a VMEbus module which was operated by VxWorks RTOS. Through the fiber links, it can deliver the master trigger and the 10 MHz base clock which is modulated with the encoded trigger message. It has a simple tree structure from a master modulator to end demodulators whose output signal edges are all aligned to the delivered base clock. As the VME module and VxWorks were very costly to maintain, they have been ported into the new SoC platform, Xilinx Spartan-3E, that has 1.2 M programmable gates and Microblaze cpu which can run uClinux on it. Using its semi-finished commercial module Suzaku-S, the unit cost of a modulator box becomes one-eighth of previous VME one. In addition, it can output 6 delayed triggers, 6 divided clocks with their own (6) gating time, whereas VME provided 6-2-2. The same network communication schemes are completely implemented on uClinux, ported from the RPC source codes running on VxWorks. As such the semi-finished SoC platform is very useful to homemade an intelligent digitizer unit, another fast latching scaler module is now designed to be made for LHD.
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Poster
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| TUD005 |
Large-scale Fusion Research System Integration Based on the Superconducting Large Helical Device and Plasma Simulator at NIFS
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352 |
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- S. Sudo, M. Emoto, R. Horiuchi, S. Imagawa, S. Imazu, S. Ishiguro, Y. Ito, O. Kaneko, K. Kawahata, M. Kojima, A. Komori, T. Mutoh, Y. Nagayama, N. Nakajima, H. Nakanishi, M. Nonomura, M. Ohsuna, N. Ohyabu, S. Okamura, H. Sugama, Y. Takeiri, H. Yamada, T. Yamamoto
NIFS, Gifu
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The representative facilities at NIFS are the superconducting Large Helical Device (LHD) and Plasma Simulator. An overview of such a large-scale fusion research system will be presented. LHD is the plasma confining machine with having superconducting helical and poloidal coils. The LHD experiment started in 1998, and stable operation under the condition of liquid He temperature with a continuous operation for half a year typically at each year has been so far successfully demonstrated for the period of 11 years. Real-time machine control and data acquisition of diagnostics are also established well for long pulse operation up to 54 min. For understanding the plasma properties, Plasma Simulator consists of a supercomputer having 77 TF computing speed and 16 TB main memory (these will be upgraded to 315 TF and 32 TB in 2012). The main aim of the Plasma Simulator is to construct LHD Numerical Test Reactor for designing an optimum reactor. Experimental remote participation to the LHD experiment and remote utilization of Plasma Simulator are well realized with the fast network SINET3. Such successful system integration will contribute to design of future large research systems.
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| WED003 |
Progress of the Virtual Laboratory for Fusion Researches in Japan
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618 |
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- T. Yamamoto, S. Ishiguro, Y. Nagayama, H. Nakanishi, S. Okamura, S. Takami
NIFS, Gifu
- K. Hiraki
IST, Tokyo
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Funding: A part of SNET is partly supported by Cyber Science Infrastracture development project of the National Institute of Informatics.
SNET is a virtual laboratory system for nuclear fusion research in Japan, it has been developed since 2001 with SINET3, which is a national academic network backbone operated by National Institute of Informatics. Twenty one sites including major Japanese universities, Japan Atomic Energy Agency and National Institute for Fusion Science (NIFS) are mutually connected on SNET with the speed of 1 Gbps in 2008 fiscal year. The SNET is a closed network system based on L2/L3VPN. Collaboration categories in SNET are as follows: the LHD remote participation; the remote use of supercomputer system; the all Japan Spherical Tokamak (ST) research program. For example, the collaborators of the first category in a remote station can control their diagnostic devices at LHD and analyze the LHD data as if they were at the LHD control room. ITER activity has started in 2007 and 'The ITER Remote Experimentation Centre' will be constructed at the Rokkasho village in Japan under ITER-BA agreement. SNET would be useful for distributing the data of ITER to Japanese universities and institutions.
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| THP107 |
Web-based Agent-oriented System for DAQ Control and Monitoring in LHD
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1 |
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- M. Ohsuna, S. Imazu, K. Kawahata, M. Kojima, Y. Nagayama, H. Nakanishi, M. Nonomura
NIFS, Gifu
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In LHD (Large Helical Device) fusion plasma experiments, 72 DAQ PCs were working for the same numbers of fusion plasma diagnostics in 2008. To establish more intelligent and autonomous operation among them, a new web-based DAQ control and monitoring system has been developed, based on the "agent-oriented" architecture. The agent on each DAQ governs the relating processes adapted to its digitizer type and OS, and on the other hand accepts/reports the commands/states from/to the monitoring service on the web server. Their communications are done on light-weight IP multicast protocols to sustain high flexibility for further extensions. A Java applet GUI can issue individual or lump-sum commands for DAQ operations and show their states in real-time, through the communications with the monitoring service. It is very advantageous in recovering from accidental DAQ unit failures so that, in typical cases of failures, the MTTR roughly becomes one third than before. The consequent reliability in the whole DAQ system, i.e. its successful operation rate, has been improved from 99.x to 99.9x in percentage.
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