12th ITPA CDBM TG MeetingCRPP EPFL, Lausanne

2007/05/08

Integrated Modeling Activities in Japan

A. FukuyamaA and T. TakizukaB

ADepartment of Nuclear Engineering, Kyoto UniversityBNaka Fusion Institute, Japan Atomic Energy Agency

in collaboration with

BPSI Working Group

Outline

1. BPSI Burning Plasma Simulation Initiative

2. TASK Core Code for Integrated Modeling (Kyoto U)

3. TASK/3D Extended version of TASK for 3D (NIFS et al.)

4. TOPICS Integrated Modeling Code (JAEA)

5. Summary

BPSI: Burning Plasma Simulation Initiative

Research Collaboration of Universities, NIFS and JAEA

Since 2002

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

Plan of BPSI

• 1st Stage: current status

◦ Development of standard dataset and module interface◦ Integrated simulation of multi-scale physics◦ Validation of modules with experimental results◦ Transport simulation in 3D helical configuration

• 2nd Stage◦ Integration of existing and newly-developed modules◦ Global integrated simulation (Core+Edge, Transport+RF+MHD,. . . )◦ Validation of modules with direct numerical simulation◦ Integrated simulation in 3D helical configuration

• 3rd Stage◦ Integrated simulation including startup and termination◦ Full integrated simulation of burning plasmas

Activities of BPSI

• Code Development◦ BPSI Framework: standard dataset and interface

— TASK code: (Kyoto U)— TASK/3D for helical plasmas: (NIFS, Kyoto U)— Predictive TOPICS for burning plasmas: (JAEA)◦ Development of integrated modeling:

— Transport-Turbulence-MHD (Kyushu U)— Core-SOL-Divertor (JAEA, CRIEPI, Tokyo U, Kyushu U)

• Support of Meetings◦ Domestic workshops (supported by RIAM, NIFS, JAEA)◦Workshop with experimentalists (supported by NF Forum)◦ US-Japan workshop with participation from EU◦ Korea-Japan workshop

Integrated Code Development Based on BPSI Framework

Integrated code: TASK, TOPICS and TASK/3D

UniversitiesNIFS JAEA

BPSI

TASK/3D TASK TOPICS

OFMCMARG2D

- - -

HINTMEGA

- - -

GNETGRM- - -

International Integrated Modeling Activities

2007/05 ITPA-CDBM-IMAGE (Lausanne)

2007/01 US-Japan JIFT WS + EU (ORNL)

2005/09 US-Japan JIFT WS + EU + KR (Kyushu U)

2004/09 US-Japan JIFT WS + EU (PPPL)

2003/12 US-Japan JIFT WS + EU (Kyoto U)

2004/11 IAEA FEC Satellite (Villamoura)

2006/04 ITPA-CDBM-Modeling (PPPL)

2006/10 ITPA-CDBM-Modeling (Chengdu)

EU:ITM-TFBecoulet

Strand

JP:BPSI2003/07

2004/03

2004/08

2005/09

2006/12

2006/05 ITER Simulation WS (Beijing)

US:FSP2002/12ISOFS

2005CSWIMCPES

2006SciDAC2 ITER:

ITPA

2003

2004

2005

2006

2007

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, MPI, MDS)— Original graphic libraries (X11, Postscript, OpenGL)◦ Development using CVS◦ Open Source: http://bpsi.nucleng.kyoto-u.ac.jp/task/)◦ Parallel Processing using MPI Library

Modules of TASK

EQ 2D Equilibrium Fixed/Free boundary, Toroidal rotationTR 1D Transport Diffusive transport, Transport modelsWR 3D Geometr. Optics EC, LH: Ray tracing, Beam tracingWM 3D Full Wave IC, AW: Antenna excitation, EigenmodeFP 3D Fokker-Planck Relativistic, Bounce-averagedDP Wave Dispersion Local dielectric tensor, Arbitrary f (u)PL Data Interface Data conversion, Profile databaseLIB Libraries LIB, MTX, MPI

Under Development

TX Transport analysis including plasma rotation and ErEG Gyrokinetic linear stability analysis

Imported from TOPICS

EQU Free boundary equilibriumNBI NBI heating

Modular Structure of TASK

EQ

TR

PL

WR

DP

Fixed-boundary equilibrium

Diffusive transport

ITPA Profile DB

JT-60 Exp. Data

Experimental Database

Simulation DB

TX

FP

WM

WX

Dynamic transport

Kinetic transport

Ray tracing

Full wave analysis

Full wave analysis including FLR

Dispersion relation

EG Gyrokinetic linear microinstabilities

EQU

NBI

TOPICS/ Free-boundary equilibrium

TOPICS/ Neutral beam injection

DataInterface

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)

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

-10 -8 -6 -4 -2 0 2 4 6 8 100

2

4

6

8

10

PPARA

PPERP

F2 FMIN = -1.2931E+01 FMAX = -1.1594E+00

0 20 40 60 80 10010-8

10-7

10-6

10-5

10-4

10-3

10-2

10-1

100

p**2

Pabs with tail

Pabs w/o tail

Pab

s [a

rb. u

nit]

r/a

Integrated Analysis of AE in ITER Plasma

• Combined Analysis◦ Equilibrium: TASK/EQ◦ Transport: TASK/TR

— Turbulent transport model: CDBM— Neoclassical transport model: NCLASS (Houlberg)— Heating and current profile: given profile◦ Full wave analysis: TASK/WM

• Stability analysis◦ Standard H-mode operation: Ip = 15 MA, Q ∼ 10◦ Hybrid operation: Ip = 12 MA, flat q profile above 1◦ Steady-state operation: Ip = 9 MA, reversed shear

Steady-State Operation

• Ip = 6→ 9 MA

• PNB = 33 MW

• PLH = 20 MW

• Q = 10.4

• βN = 1.8

Te

Ti

T [k

eV]

0.0 0.2 0.4 0.6 0.8 1.00

5

10

15

20

25

jTOT

jOH

jNB

jBS

j [M

A/m

2 ]

0.0 0.2 0.4 0.6 0.8 1.0

-0.4

0.0

0.4

0.8

1.2

nB

nαn [1

020/m

3 ]

0.0 0.2 0.4 0.6 0.8 1.00.00

0.01

0.02

0.03

0.04

q

0.0 0.2 0.4 0.6 0.8 1.00

1

2

3

4

5

Pα

PNB

PTOT

P [M

W]

0 10 20 30 40 500

20

40

60

80

PLH

IOHINB IBS

ITOT

I [M

A]

0 10 20 30 40 5002468

10

ILH

Te0

TD0

T [k

eV]

0 10 20 30 40 5005

10152025

Q

t [s]0 10 20 30 40 50

0.00.51.01.52.02.5

AE in Steady-State Operation

q profile

q

0.0 0.2 0.4 0.6 0.8 1.00

1

2

3

4

5

Alfven Continuum

ρ

Mode structure (n = 1)

Eθ

r

m=–1

m=–2

fr = 109.10 kHzfi = 0.77 kHz

Unstable core localized modePreliminary

Future Plan of the 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

Access to the TASK code

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

• Source code◦ Stable version (original part only):— Downloadable from our 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

Extended version: TASK/3D

• Motivation◦ Integrated modeling of 3D plasma in helical devices— LHD, Heliotron-J et al.◦Modeling of tokamak plasmas including 3D effects— Effects of toroidal field ripple: Toroidal rotation, RWM— Effects of magnetic islands: NTM, Transport

• Extension◦ Interface for 3D configuration◦ Transport model including Er◦Modeling of magnetic island

Modules of TASK/3D

• 3D Equilibrium:

◦ Interface to equilibrium data from VMEC or HINT◦ Interface to neoclassical transport coefficient code BSC

• Modules 3D-ready:

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

• New module: (by Y. Nakamura)

◦ EI: Time evolution of current profile in helical geometry

• Modules to be updated:

◦ TR: Diffusive transport (with an appropriate model of Er)◦ TX: Dynamic transport (with neoclassical toroidal viscosity)

Integrated modelling in JAEA

TOPICS-IB: TOPICS extended to Integrated simulation for Burning plasma

Tokamak Preduction and Interpretation Code1D transport and 2D equilibrium, MatrixInversion Method for NeoClassical Trans.

ECCD/ECH (Ray tracing, Relativistic F-P), NBCD(1 or 2D Fokker-Planck)

1D transport for each impurities,Radiation: IMPACT

Tearing/NTM, High-n ballooning,Low and Mid.-n MARG2D

Orbit following monte carlo, F-P, Stix

Transport code TOPICSTransport code TOPICSTransport code TOPICS

TransportTransport

Pedestal-SOL-DivertorPedestal-SOL-Divertor

Heating, Current DriveHeating, Current Drive

Impurity TransportImpurity Transport

MHDMHDMHD

Neutral and α particlesNeutral and α particles

Transport model in core plasma

Transport in pdestal/SOL/Divertor ELM, Neutral, impurity

Integrated modelling in JAEAIntegrated modelling in JAEA

NTM simulation by Integrated model

Modified Rutherford equationModified Rutherford equation ECCD codeECCD code

1.5 tokamak simulation code ( TOPICS )

1D transport equations for density and temperatures

Bootstrap current : Matrix Inversion method for

Hirshman & Sigmar formula

Neoclassical resistivity : Hirshman & Hawryluk model

2D MHD equilibrium : Grad-Shafranov equation

1.5 tokamak simulation code ( TOPICS )

1D transport equations for density and temperatures

Bootstrap current : Matrix Inversion method for

Hirshman & Sigmar formula

Neoclassical resistivity : Hirshman & Hawryluk model

2D MHD equilibrium : Grad-Shafranov equation

EC currentAdditionalcurrentsource

Physicalvaluesat rationalsurface

Current profile

Bootstrapcurrent, etc

Transportdegradation

Geometry& Plasmaprofiles( )

• To do the self-consistent analysis of stabilizing effect, 1.5D transport code, Modified Rutherfordequation and ECCD code are integrated.

• Neoclassical tearing mode (NTM) are important to access and tosustain high β and it relates to the transport and MHD.

• For the stabilization of NTM, profile control and ECCD injection were demonstrated in JT-60U.

Integrated modelling in JAEAIntegrated modelling in JAEA

NTM simulation with modified Rutherford equation was verified by experimental results.

Experiment (B0.5 )

0

0.5

1

1.5

9 10 11 12 13time [s]

[arb

]

~

EC: 9.5-11.5s

Island

0

0.2

0.4

0.6

0.8

1

1.2

1.4

0.4 0.5 0.6 0.7ρEC

Ra

tio

(11

.5s

/ 9.5

s)

0 0.5 1-0.5-1.5 -1(ρEC – ρq=2) / W

B0.5(Exp.)~

EC

A

A

B

C

B

C

wid

th

Rat

io (

11.5

s/9.

5s)

Experiment (B0.5 )

0

0.5

1

1.5

9 10 11 12 13time [s]

TOPICS (W)

[arb

]

~

EC: 9.5-11.5s

Island

0

0.2

0.4

0.6

0.8

1

1.2

1.4

0.4 0.5 0.6 0.7ρEC

Ra

tio

(11

.5s

/ 9.5

s)

0 0.5 1-0.5-1.5 -1(ρEC – ρq=2) / W

W(TOPICS)B0.5(Exp.)~

• Good agreement with the samecoefficient set

A

A

B

C

B

C

EC

wid

th

Rat

io (

11.5

s/9.

5s)

[A. Isayama, IAEA FEC 2006]

δ EC

*

0

0.5

1

1.5

2

0 5 10 15 20IEC [kA]

JEC/JBS=0.3 JEC/JBS=0.5

JEC/JBS=1

Complete stabilization

JT-60U

The consistent analysis shows:• ECCD width has stronger effectthan amount of EC-driven current.• Precise ECCD control has enabled complete stabilization with smaller value of jEC/jBS :JEC/JBS ~ 0.5

Integrated modelling in JAEAIntegrated modelling in JAEA

Integrated edge-pedestal model

1.5D core transport code ( TOPICS )

2D Grad-Shafranov equation1D transport & current diffusion equations

Heat & particle flows across separatrix

Boundary conditions at separatrix

SOL-divertor model (Five-point model)

Integral fluid equationsExponential radial profiles with characteristic scale length

Flux-tube geometry

ELM model : Enhance transport

2D MHDequilibrium

Eigenvalue & Eigenfunction

Linear MHD stability code ( MARG2D )

Applicable to wide range of mode numbers from low to high

Eigenvalue problem of 2D Newcomb equation

[N. Hayashi, IAEA FEC 2006]

Integrated modelling in JAEAIntegrated modelling in JAEA

ELM energy loss simulation

• Energy loss by ELMs is crucial for reducing the divertor plate lifetime and limiting the plasma confinement.

• ELM energy loss was found to decrease with increasing the collisionality in multi-machine experiments.

• The collisionality dependence is investigated.

• ELM phenomena is simulated in JT-60 parameters. Loarte, PPCF03

Stabilities of n=1-30 modes are examined in each time step.

Pedestal formation : Neoclassical transport in peripheral region and anomalous in inside region.

Integrated modelling in JT-60UIntegrated modelling in JT-60U

Bootstrap Current and SOL Transport throughCollisionality Affects the ELM Energy Loss

Higher ν*ped

Lower JBSped

Larger sped Smaller unstable regionSmaller ΔWELM

Lower κ//SOL

Higher TeSOL after ELM crash

Smaller ∇Teedge

Smaller perpendicular lossSmaller ΔWELM

interaction

SONIC

PARASOL

PIC + Monte Carlo

- Kinetic effect- Collision- Sheath, Drift- Transport etc.

D neutralC impurity

D ion

The elaborate impurity Monte Carlo code (IMPMC) has been successfully combined with divertor code [1].

New Diffusion ModelMassive parallelcomputer

[2]

[1] K. Shimizu, et al., 17th PSI (2006).[2] T. Takizuka, et al., 15th PSI (2002).

Integrated SOL-divertor code:SONICIntegrated modelling in JT-60UIntegrated modelling in JT-60U

Summary

• Integrated modeling activity in Japan is coordinated with BurningPlasma Simulation Initiative.

• Standard dataset and module interface for integrated modelinghave been proposed and partially implemented in TASK.

• The TASK code has been developed as a reference core code forBPSI and applied to the prediction of ITER plasmas.

• The development of the extended version TASK/3D has startedaiming at not only helical plasmas but also 3D effects in tokamaks.

• Predictive TOPICS has been successfully combined with variouscodes (MHD, SOL, EC) for integrated modeling.

• Benchmark test and module exchange between TASK and TOPICSare in progress.