Slide 1

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), 322-6 Oroshi, Toki 509-5292, 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 Slide 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 Slide 3 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 Slide 4 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. Slide 5 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) Slide 6 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