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Integrated Tokamak Modeling Integrated Tokamak Modeling in RUSSIA in RUSSIA Status and Plans Status and Plans S.V. Konovalov, RRC Kurchatov S.V. Konovalov, RRC Kurchatov Institute Institute

Integrated Tokamak Modeling in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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Integrated Tokamak Modeling in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute. Institutions Involved in ITM activity coordinated by Kurchatov Institute. НИИЭФА Им. Ефремова. General Strategy is parallel development of compatible modules and integrated code. - PowerPoint PPT Presentation

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Page 1: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

Integrated Tokamak Integrated Tokamak Modeling Modeling in RUSSIAin RUSSIA

Status and PlansStatus and Plans

S.V. Konovalov, RRC Kurchatov InstituteS.V. Konovalov, RRC Kurchatov Institute

Page 2: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

ITM in RFITM in RF IMAGE session, Lausanne, May 2007IMAGE session, Lausanne, May 2007 22

Institutions Involved in ITM Institutions Involved in ITM activity coordinated by activity coordinated by

Kurchatov InstituteKurchatov Institute

НИИЭФАНИИЭФАИм. Им. ЕфремоваЕфремова

Page 3: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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General Strategy is parallel General Strategy is parallel development of compatible development of compatible

modules and integrated code modules and integrated code Integration shellIntegration shell ModulesModules: : 1)Physics:1)Physics: Fixed/Free Fixed/Free

boundary equilibrium, boundary equilibrium, Ideal/Resistive/Drift/EP Ideal/Resistive/Drift/EP MHD stability, Auxiliary MHD stability, Auxiliary Heating/CD, Impurity Heating/CD, Impurity dynamics, Runaways, dynamics, Runaways, Energetic Ion effects, etc.Energetic Ion effects, etc.

2)Engineerings2)Engineerings: ITER : ITER systems, controllers, etc.systems, controllers, etc.

3)Diagnostics:3)Diagnostics: EP, H EP, H, , neutron, magnetic probes, neutron, magnetic probes, reflectometry ... reflectometry ...

Ultimate Goal is ITER simulatorsUltimate Goal is ITER simulators

Integratingcode Modules

ITERSimulators

Page 4: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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Integrating shell combines Integrating shell combines advantages of ASTRA and advantages of ASTRA and

DINADINA

Page 5: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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Automated System for TRansport Automated System for TRansport Analysis (ASTRA)Analysis (ASTRA)

MAIN ADVANTAGES:MAIN ADVANTAGES:

It is widely used for scenario development and kinetic control, for It is widely used for scenario development and kinetic control, for experimental analysis, model validation and predictive simulations. experimental analysis, model validation and predictive simulations.

It has about 20 years history of development. It is familiar to users at more It has about 20 years history of development. It is familiar to users at more then 20 sites in 4 ITER Parties which enables to expect further then 20 sites in 4 ITER Parties which enables to expect further contributions in the compatible modules development.contributions in the compatible modules development.

It comprises a large library of compatible validated and benchmarked It comprises a large library of compatible validated and benchmarked modules for the simulation of plasma transport, equilibrium, heating and modules for the simulation of plasma transport, equilibrium, heating and current drive. current drive.

It has well developed shell for modification of the physical model, It has well developed shell for modification of the physical model, automatic code generation, convenient graphics for real time interactive automatic code generation, convenient graphics for real time interactive scenario control and presentation of the result.scenario control and presentation of the result.

Allows integration with other codes through the sheared memoryAllows integration with other codes through the sheared memory

Page 6: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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ASTRA-6 upgradesASTRA-6 upgrades Fixed and Free boundary equilibrium solver (SPIDER)Fixed and Free boundary equilibrium solver (SPIDER)

MHD stability analysis – KINX (no feedbacks on transport MHD stability analysis – KINX (no feedbacks on transport modifications at the present)modifications at the present)

Impurity radiation and transport (ZIMPUR + NCLASS)Impurity radiation and transport (ZIMPUR + NCLASS)

Auxiliary Heating/CD interpolated modules (OGRAY, Auxiliary Heating/CD interpolated modules (OGRAY, STELION, DRIFT/NBI etc.)STELION, DRIFT/NBI etc.)

Grid version for optimization of the scenarios, development Grid version for optimization of the scenarios, development of the experimental strategy, producing the user friendly of the experimental strategy, producing the user friendly simplified models - SIMULATORS (CODAC, real-time control simplified models - SIMULATORS (CODAC, real-time control models , etc...)models , etc...)

Page 7: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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DINA codeDINA codeMain advantages:Main advantages:• Scenario simulation with account for Scenario simulation with account for

realistic external controllers for plasma realistic external controllers for plasma position, shape and current.position, shape and current.

• Disruption and VDE simulations with halo Disruption and VDE simulations with halo and runaway current generation. and runaway current generation.

• Simulator of ITER disruptions validated on Simulator of ITER disruptions validated on JT-60U data JT-60U data

• Interfaces with engineering codes Interfaces with engineering codes (MATLAB Simulink version) (MATLAB Simulink version)

• Reconstruction of the equilibrium Reconstruction of the equilibrium configuration using the magnetic configuration using the magnetic diagnostics datadiagnostics data

Page 8: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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DINA - MATLABDINA - MATLAB

Page 9: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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DINA - upgradesDINA - upgrades

•Improvement of transport models

•Initial stage: model for neutrals, integration with TRANSMAK

•Advanced Auxiliary Heating / CD modules

•Divertor plasma model: DINA-SOL

•User interfaces: compatibility with ASTRA shell and SCoPEShell

Page 10: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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MODULESMODULES

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Main CodesMain Codes

ScenarioScenario

ASTRA DINAASTRA DINA

ControlControl

EquilibriumEquilibrium SPIDER, PETSPIDER, PET

MHD StabilityMHD Stability KINX, NFTCKINX, NFTC

Auxiliary Heating Auxiliary Heating & CD& CD OGRAY, OGRAY,

PSTELION, ANTRESPSTELION, ANTRESParticle Motion Particle Motion

& Kinetics& Kinetics DRIFT, FPP-3D,DRIFT, FPP-3D,

VENUS-VENUS-F F

Impurity Impurity radiation & radiation & transporttransport ZIMPURZIMPUR

3D structures3D structures KLONDIKE, KLONDIKE, TYPHOONTYPHOON

Data Analysis, Neural Data Analysis, Neural Network, Visualization, Network, Visualization,

etc.:etc.: SCoPEShell SCoPEShell NNTMM, VIP, CLUNAVTNNTMM, VIP, CLUNAVT

Plasma InitiationPlasma InitiationSCENPLINTSCENPLINTTRANSMAKTRANSMAK

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Equilibrium solver SPIDEREquilibrium solver SPIDER

There are rectangular and adaptive grid versionsThere are rectangular and adaptive grid versions

-2 0 2 4 6 8 10 12 14 16

-6

-4

-2

0

2

4

6

Poloidal flux contours

2 4 6 8 10 12

-6

-4

-2

0

2

4

6

Whole grid and plasma domain. time=0

a) Rectangular – provides a) Rectangular – provides standard EQ data for other standard EQ data for other codescodes

b) Adaptive – requires no b) Adaptive – requires no additional mapping for 1.5D additional mapping for 1.5D transport simulationtransport simulation

Page 13: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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SPIDER free boundary equilibrium SPIDER free boundary equilibrium simulationssimulations

Simulation of the plasma Simulation of the plasma

initiation, VDE and initiation, VDE and disruptionsdisruptions

Good convergence for Good convergence for steep plasma current steep plasma current density and pressure density and pressure gradientsgradients

Intrinsic compatibility Intrinsic compatibility with KINX stability with KINX stability calculationscalculations

SPIDER is the base of the SPIDER is the base of the DINA codeDINA code

Page 14: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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Impurity charge state & Impurity charge state & radiation module ZIMPURradiation module ZIMPUR

ZIMPURZIMPUR – calculates radial distributions and radiation of the impurity ions in all existing charge states

It allows simulations of the high-Z impurities Ar, W, etc.

There are 2 options:

•Stand alone (atomic process rates, Z distribution, radiation, code description and demo – 50% ready)

•ASTRA module combined with NCLASS (accommodation to SPIDER equilibrium is in progress)

Page 15: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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KINX – ideal linear MHD stability KINX – ideal linear MHD stability codecode

0 0.5 1 1.5 2 2.5 30

0.5

1

1.5

iter scen2 x0=0.97 J

edge/J=-0.06 p'

edge/p'=1

p'/p'c

J ||/<J>

ballooning

bootstrap

shear reversal

101520

30

40

ITER edge stability diagramITER edge stability diagram•Pedestal j|| and p’ rescaled independently•n=∞ ballooning and kink/ballooning modes n<40

Page 16: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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KINX - RWMKINX - RWM

Levels of normal displacements (left) and perturbed magnetic field along the first

wall.

2D RWM:2D RWM:

•Benchmarking of codes used for simulation of RWM feedback control in ITER

•Calculation of transfer functions describing evolution of RWM in the presence of active control

•Calculation of N(no wall) and N(ideal wall) for different ITER plasmas

Page 17: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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KINX + TYPHOON 3D RWMKINX + TYPHOON 3D RWM

In-port coils are necessary to stabilize RWM in ITER

3D structures – TYPHOON

Inertia-free MHD plasma model + 3D vacuum vessel were developed (KINX-3D)

Regularization procedure is necessary

KINX+TYPHOON coupling

At the moment development of 3D-RWM code is temporary suspended

Page 18: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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AlfvAlfvéén mode stability in ITERn mode stability in ITER

1

1.5

2

2.5

3

3.5

4

q

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 10

0.5

1

1.5

2

2.5

3

3.5

4

sqrt()

/

A

Alfven continuum n=1 roedge=0.25 0 0.2 0.4 0.6 0.8 1

1

1.5

2

2.5

3

3.5

4

4.5

q

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

sqrt(); 2/A2 =2.4289; kinetic energy norm; stability of eq. unknown; 769 eigenvalues less than 2.45

KINX2000: Normal displacement (SFL harmonics) of n=1 mode 256256

1

2

3

4

5

6

7

8

9

10

Alfven continuum (left) and gap mode radial structure in ITER inductive scenario

Selfconsistent model for the Alfven mode evolution and associated fast ion transport (KINX + DRIFTASTRA; KINX+(VENUS+f)) is under development

Page 19: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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OFMC code DRIFTOFMC code DRIFT

Anomalous transport and losses of Anomalous transport and losses of fast ions (ripple, MHD perturbations)fast ions (ripple, MHD perturbations)

Heat loads on plasma facing elementsHeat loads on plasma facing elements NBI moduleNBI module ICRF heatingICRF heating FI distribution functionFI distribution function FI Diagnostics (NPA, scintillators)FI Diagnostics (NPA, scintillators)

Page 20: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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Exact NBI geometry Exact NBI geometry ITER, JT-60U, JETITER, JT-60U, JET

ITER NBI shine throughITER NBI shine through

-1 0 0 -8 0 -6 0 -4 0 -2 0 0 2 0 4 0 6 0 8 0 1 0 0

X (cm )

-6 0

-4 0

-2 0

0

2 0

4 0

6 0

8 0

1 0 0

Z(c

m)

4 .00 E -003

8 .00 E -003

1 .20 E -002

1 .60 E -002

2 .00 E -002

2 .40 E -002

Page 21: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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2-3D distribution of heat 2-3D distribution of heat loadload

2 4 6 8 1 0 1 2 1 4 1 6 18

10 5

11 0

11 5

12 0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

5 5 0

6 0 0

6 5 0

2 4 6 8 1 0 1 2 1 4 1 6 18

14 5

15 0

15 5

16 0

16 5

17 0

17 5

18 0

18 5

19 0

5 0 0

1 0 0 0

1 5 0 0

2 0 0 0

2 5 0 0

3 0 0 0

3 5 0 0

4 0 0 0

ITER FW and Limiter heat loads due to alpha ripple losses (in absence of the ferromagnetic inserts)

Page 22: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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Fast Ion Distribution Fast Ion Distribution FunctionFunction

#33917

0 2 0 4 0 6 0 8 0 1 0 0E k eV

0 .4

0 .6

0 .8

1 .0

1 .2

Nri

pple

/ Nno

rip

ple

O F M C

N P A

NBI distribution function and NPA spectrum in JET

Page 23: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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FFokker-okker-PPlanck lanck PPackage ackage Three-Three-DDimensionalimensional code code FPP-3DFPP-3D

•Solves 3D drift orbit averaged kinetic equation, no limits on orbit width (esp. important for RS scenario)

•Calculates radial particle, momentum and energy fluxes, bootstrap-current electron and ion components, etc.

•Non-linear problems can be solved.

•Fusion alphas, NBI and ICRF heated ion dynamics

•Particle fluxes into lost ion detectors and NPA

•Solution of inverse kinetic problems.

Fusion alphas in JET experiment

DRIFT FPP-3D simplified fast ion modules for ASTRA-DRIFT FPP-3D simplified fast ion modules for ASTRA-DINADINA Full set of NBI simulators: Monte Carlo, 3D, 2D, 1D Fokker-Plank to be finalized

Page 24: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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Nonlinear 3D MHD CodeNonlinear 3D MHD Code NFTCNFTC Simulates NTM evolution in ITER inductive scenarioSimulates NTM evolution in ITER inductive scenario Simulates seed island formation from sawtoothSimulates seed island formation from sawtooth Predicts double threshold. Needs clarification, Predicts double threshold. Needs clarification,

benchmarking with XTORbenchmarking with XTOR

Page 25: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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OGRAY ECRH/CDOGRAY ECRH/CD

0,5 0,6 0,7 0,8 0,90

2

4

6

8

10

12

14

J, A

/cm

2

ECCD for NTM stabilization in ITER

ECCD module for ASTRA (ECCD ITER simulator)

Page 26: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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ITER ICRF antenna ITER ICRF antenna simulation with ANTRES simulation with ANTRES

codecode provides impedance matrix provides impedance matrix

of multi loop, multi recess of multi loop, multi recess antenna, radiating Fast antenna, radiating Fast Waves (FW) into Waves (FW) into inhomogeneous hot large inhomogeneous hot large scale ITER plasma, with scale ITER plasma, with account for reflected waves.account for reflected waves.

evaluation of power evaluation of power capabilities of ITER ICRF capabilities of ITER ICRF antenna and optimized antenna and optimized construction of an antenna-construction of an antenna-generator matching system. generator matching system.

Analysis of potential Analysis of potential advantages of the “traveling advantages of the “traveling wave multi loop antenna”.wave multi loop antenna”.

Page 27: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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ICRF and ECRF by full wave 3D ICRF and ECRF by full wave 3D code PSTELIONcode PSTELION

Power deposition to D+ and e- at F=53MHz, N=27

•ICRF in ITER: dominant ion heating, localized off-axis CD, various heating/CD scenarios•Importance of upper hybrid resonance in ECRH, impact on ECCD stabilization of NTM•Simplified ICRF modules – ICRF ITER simulator (in progress)

Page 28: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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NNeural eural NNetwork etwork TTool for ool for MMathematical athematical MModeling.odeling.

NNTMMNNTMM performs iterative analyses and performs iterative analyses and optimization with Kohonen maps and feedforward optimization with Kohonen maps and feedforward networks. NNTMM is developed under MATLAB. It networks. NNTMM is developed under MATLAB. It has a user-friendly graphical interface where the has a user-friendly graphical interface where the user can: user can:

manipulate with input data (sort, select, etc.) manipulate with input data (sort, select, etc.) perform dimension analyses perform dimension analyses clusterize and visualize data using Kohonen maps clusterize and visualize data using Kohonen maps train feedforward network train feedforward network perform calculations with trained network perform calculations with trained network analyse network calculated data with Kohonen analyse network calculated data with Kohonen

maps maps find optimal parameters find optimal parameters

Page 29: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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Data analyses and Data analyses and optimization in numerical optimization in numerical

experimentsexperiments

NNTMM approach permitted to rise bootstrap current for NNTMM approach permitted to rise bootstrap current for 30% using 30% using the data from only 60 runs of transport code SCoPEthe data from only 60 runs of transport code SCoPE

SCoPE (transport code) calculated data using 30 runs

Neural network (trained using SCoPE data )simulating 20000 SCoPE runs. New optimal sets of parameters are found.

Page 30: Integrated Tokamak Modeling  in RUSSIA Status and Plans S.V. Konovalov, RRC Kurchatov Institute

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Possible application of Possible application of NNTMMNNTMM

Development of the effective (real Development of the effective (real time) simulator of ITER scenariostime) simulator of ITER scenarios

Optimization of the algorithms of the Optimization of the algorithms of the multi-parametric control of the multi-parametric control of the dischargedischarge

Optimization of the experimental Optimization of the experimental strategy (on the ASTRA simulations strategy (on the ASTRA simulations at present) at present)

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ITER confinement database analysis with Support Vector Machine

Kohonen map (SOM) for the data from the international global H-mode confinement database

SVM predicts that basic ITER scenarios are deeply in H-mode

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SCoPEShell: a graphical Java SCoPEShell: a graphical Java shell candidate for integrated shell candidate for integrated

codecode It is a user-friendly graphical interface where user It is a user-friendly graphical interface where user

can: can: set all input and output parameters of the set all input and output parameters of the

numerical code numerical code edit the numerical code source files edit the numerical code source files compile and run the numerical code compile and run the numerical code monitor calculations monitor calculations convert output binary files to text ones convert output binary files to text ones output all computed data to NetCDF format output all computed data to NetCDF format plot 2D and 3D numerical code output data plot 2D and 3D numerical code output data

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SCoPEShell exampleSCoPEShell example

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VIP: plasma shape VIP: plasma shape reconstructionreconstruction

Algorithm is suitable for real time simulation with feedback control .

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2007 plans for ITER 2007 plans for ITER simulationssimulations

Plasma initiation, current rump up Plasma initiation, current rump up Fast ion confinement / anomalous (including ripple) Fast ion confinement / anomalous (including ripple)

transporttransport Scenarios (sensitivity studies, control options)Scenarios (sensitivity studies, control options) Disruptions and VDEDisruptions and VDE RWM and NTM theory, modeling and possibility of RWM and NTM theory, modeling and possibility of

controlcontrol ICRF antennaICRF antenna ICRF & ECRF full wave modeling (dominant ion ICRF & ECRF full wave modeling (dominant ion

heating, off-axis CD possibilities) heating, off-axis CD possibilities) NBI heating/CD for various NB designs, diagnostic NBI heating/CD for various NB designs, diagnostic

NBINBI