LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan1/28 Control, Data.

Slides:



Advertisements
Similar presentations
Some New Data From FRC Experiment on Relaxation For discussions at Hall-Dynamo and Related Physics meeting CMSO June 10-11, 2004 at PPPL Guo et al, PRL.
Advertisements

H-1 Heliac: Parameters 3 period heliac: 1992 Major radius1m Minor radius m Vacuum chamber33m 2 Aspect ratio5+ Magnetic Field1 Tesla (0.2 DC) Heating.
Device Parameters of Heliotron J Coil System L=1/M=4 helical coil 0.96MAT Toroidal coil A0.6MAT Toroidal coil B 0.218MAT Main vertical coil 0.84MAT Inner.
Japan-US Workshop on Fusion Power Plants Related Advanced Technologies with participants from China and Korea ( Kyoto University, Uji, Japan, Feb.
9th TTF Spain September 11, 2002 B. J. Peterson, NIFS, Japan page 1 Radiative Collapse and Density Limit in the Large Helical Device.
I. Opening I-1. Welcome address U.Stroth I-2. Logistics M.Ramisch I-3. Opening remarks H.Yamada II. Definition of the goal of CWGM5 II-1. Brief review.
Effects of ICRF conditioning on the first wall in LHD N. Ashikawa, K. Saito, T. Seki, M. Tokitani, Y. Ohtawa 1), M. Nishiura, S. Masuzaki K. Nishimura.
Physics of fusion power Lecture 14: Anomalous transport / ITER.
Density Limit Studies in LHD B. J. Peterson, J. Miyazawa, K. Nishimura, S. Masuzaki, Y. Nagayama, N. Ohyabu, H. Yamada, K. Yamazaki, T. Kato, N. Ashikawa,
TH/3-1Ra Nonperturbative Effects of Energetic Ions on Alfvén Eigenmodes by Y. Todo et al. EX/5-4Rb Configuration Dependence of Energetic Ion Driven Alfven.
US-Japan Workshop on Fusion Power Plants and Related Advanced Technologies High Temperature Plasma Center, the University of Tokyo Yuichi OGAWA, Takuya.
Energy loss for grassy ELMs and effects of plasma rotation on the ELM characteristics in JT-60U N. Oyama 1), Y. Sakamoto 1), M. Takechi 1), A. Isayama.
Steady State High  N Discharges and Real-Time Control of Current Profile in JT-60U T. Suzuki 1), A. Isayama 1), Y. Sakamoto 1), S. Ide 1), T. Fujita 1),
D. Borba 1 21 st IAEA Fusion Energy Conference, Chengdu China 21 st October 2006 Excitation of Alfvén eigenmodes with sub-Alfvénic neutral beam ions in.
Y. Sakamoto JAEA Japan-US Workshop on Fusion Power Plants and Related Technologies with participations from China and Korea February 26-28, 2013 at Kyoto.
Measurement of the Plasma Driven Permeation Flux in the Spherical Tokamak QUEST S. K. Sharma 1 H. Zushi 2, I. Takagi 3, Y.Hisano 1, M. Sakamoto 2, Y. Higashizono.
Effects of global MHD instability on operational high beta-regime in LHD IAEA FEC2004, Vilamoura, Nov.3, 2004 EX3/3 IAEA FEC2004, Vilamoura, Nov.3, 2004.
Model prediction of impurity retention in ergodic layer and comparison with edge carbon emission in LHD (Impurity retention in the ergodic layer of LHD)
Simulation Study on behaviors of a detachment front in a divertor plasma: roles of the cross-field transport Makoto Nakamura Prof. Y. Ogawa, S. Togo, M.
Monte Carlo Monte Carlo Simulation Study of Neoclassical Transport and Plasma Heating in LHD S. Murakami Department of Nuclear Engineering, Kyoto University,
1 Introduction of COACK to the HIBP Control NIFS - National Institute for Fusion Science H. Ogawa, T.Inoue, Q.Tsukada, M.Yokota, M.Kojima, J.Kodaira, H.
NSTX-U NSTX-U PAC-31 Response to Questions – Day 1 Summary of Answers Q: Maximum pulse length at 1MA, 0.75T, 1 st year parameters? –A1: Full 5 seconds.
Progress of Confinement Physics Study in Compact Helical System
14 Oct. 2009, S. Masuzaki 1/18 Edge Heat Transport in the Helical Divertor Configuration in LHD S. Masuzaki, M. Kobayashi, T. Murase, T. Morisaki, N. Ohyabu,
EAST Data processing of divertor probes on EAST Jun Wang, Jiafeng Chang, Guosheng Xu, Wei Zhang, Tingfeng Ming, Siye Ding Institute of Plasma Physics,
1 MHD simulation on pellet plasmoid in LHD R. Ishizaki and N. Nakajima 6 th Japan-Korea Workshop on Theory and Simulation of Magnetic Fusion Plasmas NIFS,
(National Institute for Fusion Science, Japan)
1 Super dense core plasma due to Internal Diffusion Barrier in LHD N. Ohyabu 1), T. Morisaki 1), S. Masuzaki 1), R. Sakamoto 1), M. Kobayashi 1), J. Miyazawa.
Edge and Internal Transport Barrier Formations in CHS S. Okamura, T. Minami, T. Akiyama, T. Oishi 1, A. Fujisawa, K. Ida, H. Iguchi, M. Isobe, S. Kado.
Sagara 1 Akio SAGARA National Institute for Fusion Science, Toki , Japan Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies.
Measurements of plasma turbulence by laser scattering in the Wendelstein 7-AS stellarator Nils P. Basse 1,2, S. Zoletnik, M. Saffman, P. K. Michelsen and.
Active Control of MHDinstabilitiy 2002/11/19 S.Ohdachi et.al. Sawtooth-like phenomena in LHD S. Ohdachi, S.Yamamoto, K. Toi, K. Y.Watanabe, S.Sakakibara,
Effect of Helical Magnetic Field Ripples on Energetic Particle Confinement in LHD Plasmas T.Saida, M.Sasao, M.Isobe 1, M.Nishiura 1, S.Murakami 2, K.Matsuoka.
Improved performance in long-pulse ELMy H-mode plasmas with internal transport barrier in JT-60U N. Oyama, A. Isayama, T. Suzuki, Y. Koide, H. Takenaga,
Summary of RF Work To Date G. Taylor NSTX Monday Physics Meeting June 21, 2010 NSTX Supported by 1.
LI et al. 1 G.Q. Li 1, X.Z. Gong 1, A.M. Garofalo 2, L.L. Lao 2, O. Meneghini 2, P.B. Snyder 2, Q.L. Ren 1, S.Y. Ding 1, W.F. Guo 1, J.P. Qian 1, B.N.
1 NSTX EXPERIMENTAL PROPOSAL - OP-XP-712 Title: HHFW Power Balance Optimization at High B Field J. Hosea, R. Bell, S. Bernabei, L. Delgado-Aparicio, S.
The Stellarator Reactor Steady State operation OK Power loadsNo disruptions, no Type I ELMs High E confinementH modes High neNo Greenwald density limit.
Effect of Energetic-Ion/Bulk-Plasma- driven MHD Instabilities on Energetic Ion Loss in the Large Helical Device Kunihiro OGAWA, Mitsutaka ISOBE, Kazuo.
Presented by Yuji NAKAMURA at US-Japan JIFT Workshop “Theory-Based Modeling and Integrated Simulation of Burning Plasmas” and 21COE Workshop “Plasma Theory”
Lower Hybrid Wave Coupling and Current Drive Experiments in HT-7 Tokamak Weici Shen Jiafang Shan Handong Xu Min Jiang HT-7 Team Institute of Plasma Physics,
17th ISHW Oct. 12, 2009, Princeton, NJ, USA Effect of Nonaxisymmetric Perturbation on Profile Formation I-08 T. Morisaki, Y. Suzuki, J. Miyazawa, M. Kobayashi,
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
“Implementation and Initial Commissioning of KSTAR Integrated Control System,” Mikyung Park NFRC, KOREA The 6 th IAEA Technical Meeting,
16 th IEEE NPSS Real Time Conference 2009 May 10 – 15, 2009 IHEP Beijing China ASIPP Current Status of EAST Plasma Control and Data Acquisition Bingjia.
3D plasma response to magnetic field structure in the Large Helical Device 24th IAEA Fusion Energy Conference San Diego 8-13 October, 2012 Y asuhiro Suzuki.
Status and Plans at LHD Y. Takeiri for LHD Experiment Group
Study on Plasma Startup Scenario of Helical DEMO reactor FFHR-d1
Overview of the LHD Central Control Room Data Monitoring Environment
Numerical investigation of H-mode threshold power by using LH transition models 8th Meeting of the ITPA Confinement Database & Modeling Topical Group.
Major aims of IPP-NIFS collaboration on divertor physics
11th IAEA Technical Meeting on H-mode Physics and Transport Barriers" , September, 2007 Tsukuba International Congress Center "EPOCHAL Tsukuba",
Integrated discharge scenario
Improvement of divertor probe array for heat flux measurement of
Yasuhiro Suzuki for the LHD experiment group
Present Status and Future Plan of Helical Research in NIFS
27th IAEA Fusion Energy Conference, October 2018, Gandhinagar, India
M.Yokoyama (National Institute for Fusion Science)
K. Ida1,2, R. Sakamoto1,2, M. Yoshinuma1,2, K. Yamasaki3, T
Design window analysis of LHD-type Heliotron DEMO reactors
Summary slide for Conceptual Design Study for Heat Exhaust Management in the ARC Fusion Pilot Plant, E.A. Tolman et al., IAEA- FIP-P1-22 Introduction ARC,
ITER FIRST WALL HEAT FLUX CONTROL DEVELOPMENT
CHARACTERIZATION OF ISOTOPE EFFECT ON CONFINEMENT
• First deuterium beam operation was initiated in LHD-NBI in
H. Nakano1,3, S. Murakami5, K. Ida1,3, M. Yoshinuma1,3, S. Ohdachi1,3,
The GDT device at the Budker Institute of Nuclear Physics is an experimental facility for studies on the main issues of development of fusion systems based.
A.V.Burdakov at al. Plasma transport in linear and helical multiple-mirror systems (EX/P5-26) Budker INP ( Novosibirsk, Russia) developed Gas-Dynamic Multiple-mirror.
EAST MDSplus Log Data Management System
Stellarator Program Update: Status of NCSX & QPS
TASK3D-a analysis database
Presentation transcript:

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan1/28 Control, Data Acquisition, Data Analysis and Remote Participation Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan 1/28 on behalf of LHD group National Institute for Fusion Science (NIFS), Oroshi, Toki , Japan NIFS site: 470,000m 2 Building for Diagnostics Development LHD Control building LHD building Office Buildings Refrigerator compressor for liquid He Guest House Baseball park Tennis court Supercomputer building in LHD Y. Nagayama R1-2

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan2/28 M. Emoto, H. Nakanishi, S. Sudo, S. Imazu, S. Inagaki*, C. Iwata, M. Kojima, M. Nonomura, M. Ohsuna, M. Yoshida, K. Tsuda, H. Chikaraishi, H. Funaba, R. Horiuchi, S. Ishiguro, Y. Ito, S. Kubo, A. Mase*, T. Mito, J. Miyazawa, T. Muto, Y. Nakamura, K. Saito, R. Sakamoto, T. Seki, S. Takami, T. Yamamoto, T. Watanabe, A. Komori, O. Motojima and LHD Group NIFS, *Kyushu Univ. Related Presentations Control of Plasma/Device –Saito: P1-14 –Ito: P1-15 –Kasahara: P1-16 –Kubo: P1-17 –Chikaraishi: P1-18 –Miyazawa: P1-19 Data Acquisition/Database –Takahashi: P2-14 –Ohsuna: P2-15 –Nakanishi: P2-20 –Kojima: P2-21 Data Analysis –Emoto: O5-4 Fast Network/Remote Participation –Yamamoto: P1-38 –Tsuda: O9-1 Co-authors

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan3/28Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan3/28 Outline LHD Control –Steady state –high desity Data acquisition –PC cluster (90GB/shot) –MSS Data analysis –GUI –Web browser of Supercomputer Remote Participation –Japanese Fusion Virtual Laboratory LHD Control and Data

Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan4/28 Large Helical Device (LHD) is a steady sate machine. Magnetic field Flux surfaces Cross sections of LHD LHD has a heliotron configuration. –A twisted plasma is confined in closed flux surfaces. –No current, no disruption, super high density. Control, data acquisition and real time monitoring are challenging.

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan5/28 Objective of LHD is to clarify physics of fusion relevant plasma in steady state. For this purpose, we are developing: Superconducting magnet, High power heating (ECH, ICH, NBI) Plasma control (divertor, density, wall, position, ) and diagnostics Obtained plasma parameters: T i0 =5keV (n e =1.2x10 19 m -3 ) T e0 =10keV (n e =0.5x10 19 m -3 ) beta=5% n e0 =10 21 m -3 (T e0 =0.4 keV) W p =1.44 MJ T pulse =3,268 sec. (P ICH+ECH =0.5 MW, W heat =1.6GJ)

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan6/28 Plasma Production for 3268 sec with ICH Steady state plasma is maintained mainly by ICH. Total input energy is 1.6 GJ (world record). Magnetic axis is swung (3.65m<R ax < 3.67m) every 105 s to reduce the temperature rise of diverter plate. Kasahara: P1-16

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan7/28 Control of superconducting magnets, plasma position, ECH/ICRF heating and density in LHD Miyazawa: P1-19 Saito: P1-14 Kasahara: P1-16 Kubo: P1-17 Chikaraishi: P1-18

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan8/28 Liquid impedance matching system of ICRF Heating in LHD Feedback control of the liquid impedance matching system reduces reflected power drastically (fro 70% to 2%). Four antennas are connected to RF generators (38.47MHz, 0.5MWx4, 1 hour). Saito: P1-14 Kasahara: P1-16

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan9/28 Diffusion barrier made with H 2 pellet Injection m -3 plasma is obtained! It’s a miracle! Why no disruption nor the radiation collapse takes place? –LHD plasma may expel impurities. Sakamoto H 2 ice pellet

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan10/28 Growing number of diagnostics requires the PC cluster technology for a data acquisition system PC cluster system (LABCOM system) has benefits –Cost effective –Flexible Key technology of PC cluster system: –Data management –Maintenance for Steady state DAQ for Short pulse DAQ Nakanishi: P2-20 Kojima: P2-21 Ohsuna: P

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan11/28 Simple PC cluster system does not work. Data should be migrated from DAQ PC to the long term data storage (DVD?). Where is the data? How to get it?

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan12/28 PC cluster system requires a index server. Data acquisition PCs write the information of data to the relational data base in the index server. Clients access the index server and take the data as the index server instructs. Index server provides Where, What, and How, which are stored in the relational database (RDB). Index Server (Relational Database) where, what, how Kojima: P2-21

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan13/28 LABCOM system (2005 Model) Expansion of storage is limited due to: –Migration time of 3 layers storages –Too many servers, because each RAID has each server. Acquired data is compressed by the DAQ-PC, and migrates to RAIDs. Data in RAIDs migrates to Jukeboxes every night. Place of data is registered in the relational database in the index server.

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan14/28 Distributed Mass Storage System (MSS) using Storage Area Network (SAN) with Fibre-Channel (FC) switch FC-SAN enhances the flexibility of the data server. –A few servers can control many RAIDs. –Data migration from RAID to Jukebox is fast. Kojima: P2-21

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan15/28 LABCOM system (2007 Model) Distributed Mass Storage System on Fibre-Channel Storage Area Network Compression: ZLIB (1-D data), JPEG-LS(2-D data) Free software: LINUX (from Windows), PostgreSQL (from ObjectStore), DAQ Box: a small PC without disk and fan (from Server PC) Compact timing demodulator made of FPGA (from VME) Nakanishi: P2-20 Kojima: P2-21 Ohsuna: P2-15 Imazu OLD

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan16/28 Real time data acquisition and monitoring Data sampled with WE7000 or cPCI are stored in the memory block. Thinned data stream are sent to WEB browser to monitor in real time. Sliced full data set can be taken after the plasma shot. H. Nakanishi K. Emoto M. Kojima M. Ohsuna S. Imazu M. Yoshida Redraw every 0.1sec request 80MB/s

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan17/28 Progress of data acquisition LABCOM system takes LHD data of 90GB/shot. LABCOM system will be extended to the ITER level (1000GB/shot). Nakanishi: P2-20 Kojima: P2-21 Ohsuna: P2-15

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan18/28 NIFS serves to 450 collaborators. Collaborator’s lord should be reduced. To serve collaborators is challenging: 1.Easy tools to view and analyze data 2.WEB GUI of supercomputer 3.Remote participation system (Virtual Laboratory) SNET Japanese Virtual Laboratory for Fusion Tsuda: O9-1 Rokkasho site

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan19/28 Collaborators need easy access. A calculation server “Egcalc” provides easy data handling system. –Collaborators use standard software “X-window”. Client Software Index Server Original Codes (Fortran, C, PV- Wave, IDL) Client Software Standard Viewer X-window NIFS User’s PC Collaborator’s PC “Egcalc” LABCOM raw data server Index Server MSS LABCOM raw data server Collaborator’s effort should be minimized Installation of LHD soft wares Learning LHD computer system MSS Emoto: O5-4

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan20/28 GUI Browsers of LHD Data in X-window No software but X-window is required in user’s PC. GLABCOMV: Viewer of Raw data S. Inagaki M. Yoshida C. Iwata CHRONOUS : Viewer of Physics data GLABCOMV: Fortran95 code. Fast enough to view raw data. CHRONOUS: PERL+GRACE. Easy artwork to make viewgraphs.

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan21/28 High level data analysis system with WEB High level computer codes can be used with the WEB browser. Using the secure shell (SSH), the job is submitted to the supercomputer. Using the portable batch system (PBS), batch jobs are managed in PC cluster. Noticed by , user takes the result from calculation server. Emoto: O5-4 Data viewers on X-window GLABCOMV CHRONOUS

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan22/28 LHD Relational Database on WEB K. Emoto M. Yoshida Search key input Excel Table Output Select Display Items WEB address Link to Video & Waveform Timing of NBI, ICH Pellet Gas puff LHD shots can be searched on the WEB site using relational database system (PostgreSQL).

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan23/28 WEB calculator of LHD field lines on PC Cluster T. Watanabe M. Emoto H. Yoshida WEB browser Results Users can easily calculate LHD field line trace with WEB like “Internet shopping”. The result, which is heavy, is taken by FTP from “Egcalc” to user’s PC. configuration Coil current is calculated.

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan24/28 WEB GUI of transport analysis code on supercomputer Physicists can operate a transport code “PROCTER”, which uses PERL to manage Fortran codes on supercomputer. Both input data and results can be seen on WEB. Emoto: O5-4 M. Emoto H. Funaba S. Murakami WEB browser Results

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan25/28 Japanese Virtual Laboratory for Fusion Remote station is a LHD control room. KASTEC Kyushu University Diagnostic Control Client at Kyushu University A. Mase SUPER-SINET In the remote station at Kyushu Univ, they can operate a LHD diagnostic device “USR” and participate the LHD experiment. Tsuda: O9-1

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan26/28 Japanese Virtual Laboratory for Fusion Using the multi protocol label switching-virtual private network (MPLS-VPN) technology on SINET3, a virtual closed network is constructed. Tsuda: O9-1 Urushidani: O3-1 Yamamoto: P1-38

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan27/28 World Fusion Virtual Laboratory: from LHD to ITER Technology of Japanese Virtual Laboratory for Fusion will be useful to construct the ITER remote participation center. ITER ITER Remote participation center ( Rokkasho site ) Urushidani: O3-1 Yamamoto: P1-38

LHD Control and Data Y. Nagayama, et al.,6th IAEA-TM "Control, Data Acquisition, Remote Participation", 4-8 June 2007, Inuyama, Japan28/28 Summary Plasma control in LHD: –Steady state operation (~1 hours). –High density core plasma (~10 21 m -3 ). LABCOM: PC cluster based data acquisition system –70 data acquisition PC, ~100 GB/shot –Index server (relational database) manages data in PC-cluster. –Fibre-Channel Storage Area Network for the Mass Storage System. High level data analysis system: for collaborators –GUI data viewers on X-window –Real time data monitor on WEB –WEB for super-computing Japanese Fusion Virtual Laboratory: –Closed network using the multi protocol label switching-virtual private network (MPLS-VPN) technology –LHD remote participation and supercomputing