Status of Integrated Tokamak Modeling activity in RUSSIA (Since May 2007)

Status of Integrated Status of Integrated Tokamak Modeling activityTokamak Modeling activity

in RUSSIAin RUSSIA

(Since May 2007)(Since May 2007)

ITM in RFITM in RF IMAGE session, Naka, October 2007IMAGE session, Naka, October 2007 22

Good news!Good news!

Government approval of RF fusion Government approval of RF fusion program till 2050 with budget ~20 program till 2050 with budget ~20 G$ (August 2007)G$ (August 2007)

Rosatom put fusion plasma Rosatom put fusion plasma simulation in the list of supported simulation in the list of supported projects (September 2007)projects (September 2007)


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

Kurchatov InstituteKurchatov Institute

НИИЭФАНИИЭФАИм. Им. ЕфремоваЕфремова


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


Inverse Problems – MSU Inverse Problems – MSU proposals proposals

1.Equilibrium reconstruction

A key difference of the presented approach from traditional consists of two features. Usage of the Ohm law along with the Grad-Shafranov equation and assumption of known plasma boundary. Larger amount of input data substantially increases the accuracy of the inverse problem solution.

Toroidal current density, its components and poloidal flux function in the equatorial plane Z = 0 (Up) and dependence of p and F derivatives on normalised flux (down). Dashed line is appropriate to solution of the direct problem, solid – to the inverse with ±15 % (10% for down figure) random error in measurements of


Inverse problems - 2Inverse problems - 2

2. Reconstruction of the 2. Reconstruction of the multiharmonicmultiharmonic spectrum and spectrum and spatial structurespatial structure of plasma of plasma oscillations (SXR, magnetic oscillations (SXR, magnetic diagnostics data)diagnostics data)

3. Reconstruction of the 3. Reconstruction of the radiation source distribution radiation source distribution from photo or video data from photo or video data (SOL and divertor)(SOL and divertor)

4. Plasma boundary 4. Plasma boundary reconstruction from video reconstruction from video datadata

5. Reconstruction of the Fast 5. Reconstruction of the Fast ion distribution from NPA ion distribution from NPA datadata


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

modules and integrated code modules and integrated code Integration based onIntegration based on transport transport

code (ASTRA + DINA)code (ASTRA + DINA) ModulesModules: : 1)Physics:1)Physics: Fixed/Free boundary Fixed/Free boundary

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

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

3)Diagnostics:3)Diagnostics: EP, H EP, H, neutron, , neutron, magnetic, reflectometry…magnetic, reflectometry…

ONLY FREE SOFTWAREONLY FREE SOFTWARE to be to be used for ITMused for ITMUltimate Goal is ITER simulatorsUltimate Goal is ITER simulators

Integratingcode Modules

ITERSimulators


Tactics:Tactics:(survival)(survival)

Urgent tasks specified by ITER IO are the principal driver of ITM in RFUrgent tasks specified by ITER IO are the principal driver of ITM in RF Plasma start up and terminationPlasma start up and termination RWM controlRWM control DNB design specificationsDNB design specifications ……

Involve computing science and technology specialist into ITM activity Involve computing science and technology specialist into ITM activity (MSU profs. and (MSU profs. and studentsstudents) )

Grid and MPI (ASTRA-grid (potential tool for experimental strategy Grid and MPI (ASTRA-grid (potential tool for experimental strategy development, Fast Ions – OFMC (non symmetrical perturbations development, Fast Ions – OFMC (non symmetrical perturbations (TBM) require huge CPU time, (TBM) require huge CPU time, δδf – multi-D distribution function)f – multi-D distribution function)

ITM Workflow (Kepler, CPO, other options) – first meeting next ITM Workflow (Kepler, CPO, other options) – first meeting next weekweek

Data manning Data manning

Get closer to the credited diagnostics developmentGet closer to the credited diagnostics development


Plasma Start up and Plasma Start up and TerminationTermination


Development of scenarios of plasma start up Development of scenarios of plasma start up (incl. initiation) and termination, in (incl. initiation) and termination, in

particular, design and simulation of ITER PF particular, design and simulation of ITER PF systemsystem

Collaboration between Efremov Inst. And Collaboration between Efremov Inst. And Kurchatov inst.Kurchatov inst.

CODES involved (Efremov Inst.):CODES involved (Efremov Inst.):SCENPLINTSCENPLINT – 0D plasma initiation model – 0D plasma initiation model (prefilled gas pressure, impurity content, (prefilled gas pressure, impurity content, ECRF power, plasma resistance)ECRF power, plasma resistance)TRANSMAKTRANSMAK – PF system characteristics, – PF system characteristics, currents induced in the conducting currents induced in the conducting elements, model of the power supplyelements, model of the power supply


DINA codeDINA code

Free boundary equilibrium solverFree boundary equilibrium solver 1D transport1D transport Eddy currents in VVEddy currents in VV Model of power supplyModel of power supply Feed back and feed forward control Feed back and feed forward control

of plasma current, plasma position of plasma current, plasma position and shapeand shape


DINA simulation of the VDEDINA simulation of the VDE


Integrated code for simulation Integrated code for simulation of plasma start up and of plasma start up and

terminationtermination DINA + SCENPLINT + TRANSMAK = New Code Revised models for neutrals (1D instead of

0D), plasma initiation with smooth transition to current rump-up stage, impurity radiation and transport.

User interfaces: compatibility with ASTRA shell

Validation against experimental data Comparison with ASTRA simulation


RWM Control in ITERRWM Control in ITER


Development of new 3D code Development of new 3D code for simulation of RWM control for simulation of RWM control

in ITER in ITER Theory background: review of the Theory background: review of the

existing models, plasma rotation effects, existing models, plasma rotation effects, error field amplifications, etc. (V.D. error field amplifications, etc. (V.D. Pustovitov, to be presented at ITPA MHD Pustovitov, to be presented at ITPA MHD group next week)group next week)

2D KINX-RWM to be upgraded and 2D KINX-RWM to be upgraded and combined with 3D transient combined with 3D transient electromagnetic analysis of tokamaks – electromagnetic analysis of tokamaks – TYPHOON codeTYPHOON code


KINX - RWMKINX - RWM

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

wall.

•KINX-RWM is capable to treat realistic divertor plasma configurations with self-consistent treatment of the separatrix at the plasma boundary.•Thoroughly benchmarked against the analytic models and other stability codes. •Proved to provide high accuracy of the computed growth rates, mode structures and transfer functions describing evolution of RWM in the presence of active control


KINX + TYPHOON 3D RWMKINX + TYPHOON 3D RWMTYPHOON is electromagnetic analysis of complex 3D conducting structures, used for ITER magnetic system design

The experience already gained from the KINX-TYPHOON coupling for the ideal MHD growth rate calculations, taking into account the 3D VV with port openings, will allow fast and efficient implementation of the multi-mode 3D RWM code

High flexibility of the 3D conductor description inherent to the TYPHOON and vast expertise in the ITER plasma control will allow reliable estimates of the feedback coil efficiency for different options of the control system


Fast Particle PhysicsFast Particle Physics


Main problems from FPP to Main problems from FPP to contribute in ITMcontribute in ITM

Confinement, loss (FW loading), power Confinement, loss (FW loading), power and momentum transfer to plasma and momentum transfer to plasma components (heating, CD, plasma components (heating, CD, plasma rotation)rotation)

FP driven instabilities (AE family, EPM FP driven instabilities (AE family, EPM etc.)etc.)

Self consistent simulation of Self consistent simulation of instabilities and transportinstabilities and transport

FP diagnostics simulationFP diagnostics simulation


FPP codes -1: OFMC code DRIFTFPP codes -1: OFMC code DRIFT Anomalous Anomalous

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

Heat loads on Heat loads on plasma facing plasma facing elementselements

MAPPING option with MAPPING option with time step equal to time step equal to bounce period (1/2 bounce period (1/2 for trapped ions)for trapped ions)

NBI moduleNBI module ICRF heatingICRF heating FI distribution FI distribution

functionfunction Power and Power and

momentum transfer momentum transfer to plasma speciesto plasma species

FI Diagnostics (NPA, FI Diagnostics (NPA, scintillators, MSE, scintillators, MSE, CX)CX)

-1 .4 -1 .2 -1.0 -0.8 -0.6 -0 .4 -0 .2 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4

Xw all (m )

-1.6

-1.4

-1.2

-1.0

-0.8

-0.6

-0.4

-0.2

Zw

all (

m)

200

400

600

800

1000

1200

1400

1600

1800

2000

2200

2400

2600

2800

3000

3200

3400

FW loading due to perpendicularly injected DNB


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


Comments on ITER NBI and Comments on ITER NBI and ICRF modulesICRF modules

NBINBI NUBEAM – 2D particle orbits, thus ripple effect is treated in NUBEAM – 2D particle orbits, thus ripple effect is treated in

terms of stochastic diffusion loss, AE – in a similar way (i.e. in terms of stochastic diffusion loss, AE – in a similar way (i.e. in a form of effective diffusion coefficients). Applicability is a form of effective diffusion coefficients). Applicability is limited.limited.

ASTRA-NBI – zero banana, no bounce averaging – potential ASTRA-NBI – zero banana, no bounce averaging – potential overestimation of the off-axis CDoverestimation of the off-axis CD

Solution – approximation of the DRIFT results for transport. Solution – approximation of the DRIFT results for transport. Implementation of the bounce average technique (already Implementation of the bounce average technique (already done in MAPPING part) into ASTRA-NBIdone in MAPPING part) into ASTRA-NBI

ICRFICRF ICRF effect is treated in assymptotic approximation, wrong ICRF effect is treated in assymptotic approximation, wrong

near the axis, errors in simulation of the central ICRF heating. near the axis, errors in simulation of the central ICRF heating. Needs selfconsistent simulation with Full Wave modelling Needs selfconsistent simulation with Full Wave modelling


FPP codes-2: FFPP codes-2: Fokker-okker-PPlanck lanck PPackage ackage Three-DThree-Dimensionalimensional 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


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. FP drive and dumping mechanisms to be included.

Consistency with equilibrium calculations, setting the separatrix shape could be of principal importance (see also Medvedev’s report in Sept. meeting)


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


2007-2008 plans for ITER 2007-2008 plans for ITER simulationssimulations

Plasma start-up and termination Plasma start-up and termination RWM theory, code development, modeling and RWM theory, code development, modeling and

control optionscontrol options FPP – NBI modules, code development for self FPP – NBI modules, code development for self

consistent simulation of the AE excitation and consistent simulation of the AE excitation and associated FP transportassociated FP transport

Reorganization of the codes according to ITER ITM Reorganization of the codes according to ITER ITM strategystrategy

Detailed description of the physics model and Detailed description of the physics model and mathematical algorithms employed – key issue mathematical algorithms employed – key issue for successful benchmarking and mutual for successful benchmarking and mutual progress!progress!

Status of Integrated Tokamak Modeling activity in RUSSIA (Since May 2007)

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