Agenda of Opening Session at CWGM5
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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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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 


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


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



“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


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.


High ion temperature 5 6 kev is achieved by enhancing ion heating
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


New perpendicular NBI much improves heating

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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