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

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

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

Revision of LHD Experiment Technical Guide

“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

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.

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

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