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I. Opening   I-1. Welcome address   U.Stroth 

Agenda of Opening Session at CWGM5. I. Opening   I-1. Welcome address   U.Stroth  I-2. Logistics  M.Ramisch  I-3. Opening remarks H.Yamada

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I. Opening   I-1. Welcome address   U.Stroth 

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  1. Agenda of Opening Session at CWGM5 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 and input from CWGM4  M.Yokoyama  II-2. Information of ISHW2009   A.Dinklage  II-3. Discussion to get consensus  III.  Linkage with other activities  III-1. Messages from the discussion on ITPA   E.Ascasibar, A.Dinklage  III-2. ITPA view in the edge/divertor topic P.Tabares  III-3. Discussion  IV. Information about activities and international collaborations IV-1. Japan LHD, Heliotron J, etc.   H.Yamada, S.Yamamoto IV-2. Spain   TJ-II, etc.   E.Ascasibar  IV-3. Germany  W7-X, etc.  A.DinklageIV-4. USA  HSX, etc.   J.Harris 

  2. LHD 13th Experimental Campaign in 2009 Task 10 theme groups Mission oriented : High density, High beta, High Ti, Steady state Physics oriented : Core transport, SOL/Divertor, MHD, High energetic particles, Wave physics Engineering oriented : Device engineering 47 days  about 7,000 plasma discharges

  3. Super computer 77TF (2009) 315TF (2012) Nearest Plan 13th experimental Campaign in 2009  20-barrel pellet injector  density limit and quasi-steady state operation of IDB/SDC  Pulsed power supplies for poloidal coils  further investigation of real time Rax control  Steady state gyrotrons 0.6 MW in CW New initiative of fusion engineeringPWI Careful work-out plan for significant upgrade in 2010 (14th exp. camp.) Closed divertor 2 inboard sections without cryo-pump NBI #5 perpendicular, 60 keV  total NBI power30 MW Plasma simulator Collaboration network

  4. Revision of LHD Experiment Technical Guide

  5. “Impurity hole” is established with increase in ion temperature •  Profile of carbon impurities becomes extremely hollow • with increase in Ti while electron density profile remains flat. •  unlike tokamak ITB •  Suppression of impurity in the core is enhanced with ion temperature gradient. • Even with carbon pellet injection, carbon is expelled with outward convection. • nC(0)/ne(0) << 1 % •  contradict prediction by neoclassical transport with negative radial electric field Soft X-ray image

  6. LHD is exploring high-performance net-current free plasmas High beta <b> = 5.1 % at B = 0.425 T <b>  5 % is maintained for > 100 tE High density ne(0) = 1.21021m-3 1.5 atmospheric pressure at B = 2.5 T  an innovative concept of super dense core reactor ( ignition at T(0) = 6-7 keV) High ion temperature Ti = 5.6 keV at ne = 1.61019m-3 accompanied by impurity hole Long pulse : 0.6 MW for 1 hour n tE T = 5  1019 m-3 s keV In 2008, 7,000 plasma discharges were served for cooperative researches.

  7. High ion temperature (5.6 keV) is achieved by enhancing ion heating  Ion temperature profile is peaked, where the gradient of ion temperature is enhanced in the core Ti (0) = 5.6 keV atne(0) = 1.6x1019m-3Ti (0) > Te (0)  Moderate Internal Transport Barrier  High ion temperature is accompanied with “impurity hole” r=0.49 r=0.59

  8. New perpendicular NBI much improves ion transport study - High-power NBI of 23 MW in total -  4 beam lines of NBI = 3 tangential + 1 perpendicular ( + 1 perpendicular in 2010) Tangential beams • 16 MW in total, ENBI = 180 kV with negative-ion sources • Primarily electron heating • Less fraction of trapped particles 180keV-tangential NB injector Perpendicular beam • 7 MW, ENBI = 40kV with positive-ion sources • Ion heating (Ti(0) = 5.6 keV) • works as a diagnostic beam for CXRS (Ti, Vf, Vq, Er) • Confinement of trapped particles secured by geometrical optimization 40keV-perpendicular NB injector

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