TASK: Integrated Simulation Code - Kyoto U

32
Workshop on Kinetic Theory in Stellarators Kyoto University, 2006/09/20 TASK: Integrated Simulation Code A. Fukuyama and M. Honda Department of Nuclear Engineering, Kyoto University presented by N. Nakajima (NIFS) Contents BPSI: Burning Plasma Simulation Initiative TASK: Core Code for Integrated Modeling Consideration on TASK/3D Summary

Transcript of TASK: Integrated Simulation Code - Kyoto U

Page 1: TASK: Integrated Simulation Code - Kyoto U

Workshop on Kinetic Theory in StellaratorsKyoto University, 2006/09/20

TASK: Integrated Simulation Code

A. Fukuyama and M. HondaDepartment of Nuclear Engineering, Kyoto University

presented byN. Nakajima (NIFS)

Contents

• BPSI: Burning Plasma Simulation Initiative

• TASK: Core Code for Integrated Modeling

• Consideration on TASK/3D

• Summary

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Burning Plasma Simulation

•Why needed?◦ To predict the behavior of burning plasmas◦ To develop reliable and efficient schemes to control them

•What is needed?◦ Simulation describing a burning plasma:— Whole plasma (core & edge & divertor & wall-plasma)— Whole discharge

(startup & sustainment & transients events & termination)— Reasonable accuracy (validation with experimental data)— Reasonable computer resources (still limited)

• How can we do?◦ Gradual increase of understanding and accuracy◦ Organized development of simulation system

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BPSI: Burning Plasma Simulation Initiative

Research Collaboration among Universities, NIFS and JAEA

Since 2002

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Targets of BPSI

• Framework for collaboration of various plasma simulation codes

◦ Common interface for data transfer and execution control◦ Standard data set for data transfer and data storage◦ Reference core code: TASK◦ Helical configuration: included

• Physics integration with different time and space scales

◦ Transport during and after a transient MHD events◦ Transport in the presence of magnetic islands◦ Core-SOL interface and . . .

• Advanced technique of computer science

◦ Parallel computing: PC cluster, Scalar-Parallel, Vector-Parallel◦ Distributed computing: GRID computing, Globus, ITBL

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Integrated Code Development Based on BPSIFramework

Integrated code: TASK and TOPICS

UniversitiesNIFS JAEA

BPSI

TASK/3D TASK TOPICS

OFMCMARG2D

- - -

HINTMEGA

- - -

GNETGRM- - -

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TASK Code

• Transport Analysing System for TokamaK

• Features◦ Core of Integrated Modeling Code in BPSI— Modular structure— Reference data interface and standard data set◦ Various Heating and Current Drive Scheme— EC, LH, IC, AW, NB◦ High Portability— Most of library routines included (except LAPACK and MPI)— Own graphic libraries (X11, eps, OpenGL)◦ Development using CVS (Concurrent Version System)— Open Source (Pre-release with f77: http://bpsi.nucleng.kyoto-u.ac.jp/task/)◦ Parallel Processing using MPI Library◦ Extension to Toroidal Helical Plasmas

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Modules of TASK

EQ 2D Equilibrium Fixed/Free boundary, Toroidal rotation

TR 1D Transport Diffusive transport, Transport models

WR 3D Geometr. Optics EC, LH: Ray tracing, Beam tracing

WM 3D Full Wave IC, AW: Antenna excitation, Eigen mode

FP 3D Fokker-Planck Relativistic, Bounce-averaged

DP Wave Dispersion Local dielectric tensor, Arbitrary f (u)

PL Data Interface Data conversion, Profile database

LIB Libraries

Under Development

TX Transport analysis including plasma rotation and ErWA Global linear stability analysisWI Integro-differential wave analysis (FLR, k · ∇B � 0)

All developed in Kyoto U

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Modular Structure of TASK

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Data Interface Layer PL

• Role of Interface Layer◦ To keep the present status of plasma◦ To store the history of plasma◦ Interface to file system◦ Interface to experimental profile database◦ Interface to simulation profile database

• Data to be stored◦ Standard dataset— Shot data, Device data— Equilibrium data, Metric data— Fluid plasma data, Kinetic plasma data— Dielectric tensor data, Full wave data, Ray/Beam tracing data◦ User-defined data

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Standard Dataset (interim)

Shot dataMachine ID, Shot ID, Model ID

Device data: (Level 1)RR R m Geometrical major radiusRA a m Geometrical minor radiusRB b m Wall radiusBB B T Vacuum toroidal mag. fieldRKAP κ Elongation at boundaryRDLT δ Triangularity at boundaryRIP Ip A Typical plasma current

Equilibrium data: (Level 1)PSI2D ψp(R, Z) Tm2 2D poloidal magnetic fluxPSIT ψt(ρ) Tm2 Poloidal magnetic fluxPSIP ψp(ρ) Tm2 Poloidal magnetic fluxPPSI p(ρ) MPa Plasma pressureTPSI T (ρ) Tm BφRQPSI 1/q(ρ) Safety factor

Metric data1D: V ′(ρ), 〈∇V〉(ρ), · · ·2D: gi j, · · ·3D: gi j, · · ·

Fluid plasma dataNSMAX s Number of particle speciesPA As Atomic massPZ0 Z0s Charge numberPZ Zs Charge state numberPN ns(ρ) m3 Number densityPT Ts(ρ) eV TemperaturePU usφ(ρ) m/s Toroidal rotation velocity

Kinetic plasma dataFP f (p, θp, ρ) momentum dist. fn at θ = 0

Dielectric tensor dataCEPS ↔ε (ρ, χ, ζ) Local dielectric tensor

Full wave field dataCE E(ρ, χ, ζ) V/m Complex wave electric fieldCB B(ρ, χ, ζ) Wb/m2 Complex wave magnetic field

Ray/Beam tracing field dataRRAY R(�) m R of ray at length �ZRAY Z(�) m Z of ray at length �PRAY φ(�) rad φ of ray at length �CERAY E(�) V/m Wave electric field at length �PWRAY P(�) W Wave power at length �DRAY d(�) m Beam radius at length �VRAY u(�) 1/m Beam curvature at length �

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Execution Control Interface in BPSI

• Example for TASK/TRTR INIT Initialization (Default value) BPSX INIT(’TR’)TR PARM(ID,PSTR) Parameter setup (Namelist input) BPSX PARM(’TR’,ID,PSTR)TR PROF(T) Profile setup (Spatial profile, Time) BPSX PROF(’TR’,T)TR EXEC(DT) Exec one step (Time step) BPSX EXEC(’TR’,DT)TR GOUT(PSTR) Plot data (Plot command) BPSX GOUT(’TR’,PSTR)TR SAVE Save data in file BPSX SAVE(’TR’)TR LOAD load data from file BPSX LOAD(’TR’)TR TERM Termination BPSX TERM(’TR’)

• Module registrationTR STRUCT%INIT=TR INITTR STRUCT%PARM=TR PARMTR STRUCT%EXEC=TR EXEC· · ·BPSX REGISTER(’TR’,TR STRUCT)

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Self-Consistent Wave Analysis with Modified f (u)

• Modification of velocity distribution from Maxwellian

◦ Absorption of ICRF waves in the presence of energetic ions◦ Current drive efficiency of LHCD◦ NTM controllability of ECCD (absorption width)

• Self-consistent wave analysis including modification of f (u)

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Development of Self-Consistent Wave Analysis

• Code Development in TASK◦ Ray tracing analysis with arbitrary f (v): Already done◦ Full wave analysis with arbitrary f (v): Completed◦ Fokker-Plank analysis of ray tracing results: Already done◦ Fokker-Plank analysis of full wave results: Almost competed◦ Self-consistent iterative analysis: Preliminary

• Tail formation by ICRF minority heatingMomentum Distribution Tail Formation Power deposition

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CDBM Transport Model: CDBM05

• Thermal Diffusivity (Marginal: γ = 0)

χTB = F(s, α, κ, ωE1)α3/2 c2

ω2pe

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E × B rotation shear ωE1 ≡ r2

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Comparison of Transport Models: ITPA Profile DB

Deviation of Stored EnergyCDBM CDBM05

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Page 28: TASK: Integrated Simulation Code - Kyoto U

Transport Modeling in Helical Plasma

• Neoclassical toroidal viscosity

• Negative magnetic shear

• Preliminary Result◦ NBI heating (P = 5 MW) : Order of magnitude slower rotation

0.0 0.2 0.4 0.6 0.8 1.00.0

0.1

0.2

0.3

0.4

0.5

r [m]

n e [1

020 m

-3]

0.0 0.2 0.4 0.6 0.8 1.0

−1.6

−1.2

−0.8

−0.4

0.0

r [m]

u iφ

[m/s

]

0.0

0.4

0.8

1.2

1.6

0.0 0.2 0.4 0.6 0.8 1.0r [m]

Te

[keV

]

0.0 0.2 0.4 0.6 0.8 1.0

−4

−2

0

2

4

r [m]

Er [

kV/m

]

Page 29: TASK: Integrated Simulation Code - Kyoto U

Future Plan of TASK code

Fixed/Free Boundary Equilibrium EvolutionEqulibrium

Core Transport 1D Diffusive TR

1D Dynamic TR

Kinetic TR 2D Fluid TR

SOL Transport 2D Fluid TR

Neutral Tranport 1D Diffusive TR Orbit Following

Energetic Ions Kinetic Evolution Orbit Following

Ray/Beam Tracing Beam PropagationWave Beam

Full Wave Kinetic ε Gyro Integral ε Orbit Integral ε

Stabilities Tearing ModeSawtooth Osc.

Resistive Wall Mode

Turbulent Transport

ELM Model

CDBM Model Linear GK + ZF

Diagnostic Module

Control Module

Plasma-Wall Interaction

Present Status In 2 years In 5 years

Systematic Stability Analysis

Start Up Analysis

Nonlinear ZK + ZF

Page 30: TASK: Integrated Simulation Code - Kyoto U

Extension to TASK/3D

• 3D Equilibrium:

◦ Interface to equilibrium data from VMEC or HINT

• Modules 3D-ready:

◦WR: Ray and beam tracing◦WM: Full wave analysis

• Modules to be updated:

◦ TR: Diffusive transport (with an appropriate model of Er)◦ TX: Dynamical transport (with neoclassical toroidal viscosity)◦ FP: Fokker-Planck analysis (with helical ripple trapping)

• Modules to be added:

◦ EI: Time evolution of current profile in helical geometry

Page 31: TASK: Integrated Simulation Code - Kyoto U

Summary

•We are developing TASK code as a reference core code for burningplasma simulation based on transport analysis.

• Standard dataset and module interface are being implemented.

• Preliminary results of self-consistent analysis of wave heatingand current drive describing the time evolution of the momentumdistribution function and its influence on the wave propagation andabsorption have been obtained.

• Extension to 3D configuration is on-going in collaboration withDr. Y. Nakamura and NIFS. (See Next Presentation)

Page 32: TASK: Integrated Simulation Code - Kyoto U

Access to TASK code

• Required Environment◦ Unix-like OS (Linux, Mac OSX, · · ·)◦ X-window system◦ Fortran95 compiler (gfortran, g95, ifort, pgf95, xlf95, sxf90, · · ·)

• Source code◦ Stable version: Web site (http://bpsi.nucleng.kyoto-u.ac.jp/task/)◦ Latest version: CVS tree (Read only) [password required]◦ Developer: CVS tree (R/W) [account required]

• User support◦ Uniform user interface◦ English guidebook in preparation: by the end of 2006