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1/7 M.Yokoyama, ITPA-IOS Kyoto Oct. 2011 Development and application of integrated transport code to LHD plasmas M.Yokoyama (National Institute for Fusion Science) for TASK3D collaborators

Development and application of integrated transport code to LHD plasmas

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Development and application of integrated transport code to LHD plasmas. M.Yokoyama (National Institute for Fusion Science) for TASK3D collaborators. TASK3D Objectives. - PowerPoint PPT Presentation

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Page 1: Development and application of integrated transport code  to LHD plasmas

1/7M.Yokoyama, ITPA-IOS Kyoto Oct. 2011

Development and application of integrated transport code       

     to LHD plasmas

M.Yokoyama (National Institute for Fusion Science)

for TASK3D collaborators

Page 2: Development and application of integrated transport code  to LHD plasmas

2/7M.Yokoyama, ITPA-IOS Kyoto Oct. 2011

TASK3D Objectives• Extension of integrated code (TASK) applicability to

general toroidal plasmas (stellarator-heliotron plasmas)

• S-H specific physics• 3D feature• Module extension/modification based on TASK

• LHD experiment : – integrated analysis– prediction, operation scenario – validation

Page 3: Development and application of integrated transport code  to LHD plasmas

3/7M.Yokoyama, ITPA-IOS Kyoto Oct. 2011

Stellarator-Heliotron specific physics

   Neoclassical (NC) diffusion (3D configuration, Er)

   Er determined by NC ambipolar condition

NBI deposition including re-entering effects

Impact of pressure driven MHD instability on pressure profile

3D feature

3D equilibrium

Evolution of rotational transform instead of

the current evolution (easier to include 3D effects)

Heating modules incorporating 3D equilibrium

Module Extension/modification

DGN/LHD

ER

MORH

VMEC

NEWBOZ

HINT2

EI

MSSH

WMLHDGaussFIT3D

Page 4: Development and application of integrated transport code  to LHD plasmas

4/7M.Yokoyama, ITPA-IOS Kyoto Oct. 2011

TA

SK

3D

EQ

TRTX

FP

WR

WMDP

Fixed-boundary equilibrium

Diffusive transport

Dynamic transport

Kinetic transport

Ray and beam tracing

Full wave analysis (ICH)

Wave dispersion

NBI analysis (Guiding Center)

TASK

FIT3D

TASKTASK3D: module extension/modification

Heating in LHD

3D Physics

3D Equilibrium

EIER

DGN/LHD

VMEC

current (iota) evolution

radial electric field

Neoclassical diffusion coefficient DB

3D equilibrium (nested surface)

HINT2 3D equilibrium (w/o nested surface assumption)

MSSH MHD instability’s impact on pressure profile

MORH NBI analysis (Re-entering)

LHDGauss Ray tracing (ECH)

BOOZER 3D equilibrium in Boozer coordinates

Page 5: Development and application of integrated transport code  to LHD plasmas

5/7M.Yokoyama, ITPA-IOS Kyoto Oct. 2011

Predictive simulation by a part of TASK3D

TR1D diffusion transport equation

~ Temperature profile variation for NBI heated plasmas ~

VMEC3D equilibrium

FIT3DNBI deposition

ERradial electric field

DGN/LHDNC diffusion coeff. DB

Gyro-Bohm

Boozer

Page 6: Development and application of integrated transport code  to LHD plasmas

6/7M.Yokoyama, ITPA-IOS Kyoto Oct. 2011

Predictive simulation by a part of TASK3D

Rax=3.60m , B=-2.75T: equilibrium fixed5 beam lines appliedDensity profile : fixed

n0=2e19

n0=4e19

n0=6e19

n0=2e19

n0=4e19

n0=6e19

•Dedicated experiment was conducted in Sep. 2011.•Anomalous transport modelling, track of configuration change, etc.. towards increased predictability: validation study -> Operation scenario for high-performance steady-state LHD plasmas

Page 7: Development and application of integrated transport code  to LHD plasmas

7/7M.Yokoyama, ITPA-IOS Kyoto Oct. 2011

Joint experiment/database/analysis/papers

Coordinated Working Group Meeting

(CWGM)

The gateway to “3D” issues

Helical Plasmas : Diversity Systemization