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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.

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Presentation on theme: "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."— Presentation transcript:

1 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. JapanLHD, Heliotron J, etc. H.Yamada, S.Yamamoto IV-2. Spain TJ-II, etc. E.Ascasibar IV-3. Germany W7-X, etc. A.Dinklage IV-4. USA HSX, etc. J.Harris Agenda of Opening Session at CWGM5

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4 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 LHD 13th Experimental Campaign in 2009

5 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 R ax control  Steady state gyrotrons 0.6 MW in CW 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 power 30 MW Super computer 77TF (2009) 315TF (2012) Plasma simulator New initiative of fusion engineering PWI Collaboration network

6 Revision of LHD Experiment Technical Guide

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9 “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. n C (0)/n e (0) << 1 %  contradict prediction by neoclassical transport with negative radial electric field Soft X-ray image

10 High beta = 5.1 % at B = T  5 % is maintained for > 100  E High density n e (0) = 1.2  m 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 T i = 5.6 keV at n e = 1.6  m -3 accompanied by impurity hole Long pulse : 0.6 MW for 1 hour n  E T = 5  m -3 s keV LHD is exploring high-performance net-current free plasmas In 2008, 7,000 plasma discharges were served for cooperative researches.

11 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 T i (0) = 5.6 keV at n e (0) = 1.6x10 19 m -3 T i (0) > T e (0)  Moderate Internal Transport Barrier  High ion temperature is accompanied with “impurity hole” 11/16  =0.49  =0.59

12 40keV-perpendicular NB injector 4 beam lines of NBI = 3 tangential + 1 perpendicular ( + 1 perpendicular in 2010) Perpendicular beam 7 MW, E NBI = 40kV with positive-ion sources Ion heating (T i (0) = 5.6 keV) works as a diagnostic beam for CXRS (T i, V , V , E r ) Confinement of trapped particles secured by geometrical optimization Tangential beams 16 MW in total, E NBI = 180 kV with negative-ion sources Primarily electron heating Less fraction of trapped particles New perpendicular NBI much improves ion transport study - High-power NBI of 23 MW in total - - High-power NBI of 23 MW in total - 180keV-tangential NB injector


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