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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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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
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Institutions Involved in ITM Institutions Involved in ITM activity coordinated by activity coordinated by
Kurchatov InstituteKurchatov Institute
НИИЭФАНИИЭФАИм. Им. ЕфремоваЕфремова
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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
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Integrating shell combines Integrating shell combines advantages of ASTRA and advantages of ASTRA and
DINADINA
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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
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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...)
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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
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DINA - MATLABDINA - MATLAB
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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
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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
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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
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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)
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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
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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
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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
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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
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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)
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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
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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)
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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
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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
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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
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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)
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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”.
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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)
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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
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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.
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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