integrated full-wave modeling of icrf heating in tokamak

29
EPS PPC 2007, Warsaw, Poland D1-005, 2007/07/02 Integrated Full-Wave Modeling of ICRF Heating in Tokamak Plasmas A. Fukuyama , S. Murakami, T. Yamamoto, H. Nuga Department of Nuclear Engineering, Kyoto University, Kyoto 606-8501, Japan 1. Introduction 2. Integrated tokamak modeling code: TASk 3. Modiļ¬cation of velocity distribution function 4. Integral formulation of full wave analysis 5. Summary

Upload: others

Post on 18-Oct-2021

7 views

Category:

Documents


0 download

TRANSCRIPT

Page 1: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

EPS PPC 2007, Warsaw, PolandD1-005, 2007/07/02

Integrated Full-Wave Modeling

of ICRF Heating in Tokamak Plasmas

A. Fukuyama, S. Murakami, T. Yamamoto, H. Nuga

Department of Nuclear Engineering, Kyoto University,Kyoto 606-8501, Japan

1. Introduction2. Integrated tokamak modeling code: TASk3. Modification of velocity distribution function4. Integral formulation of full wave analysis5. Summary

Page 2: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Introduction(1)

ICRF Waves in Burning Plasmas

ICRF waves

Fusion reaction

Energetic

ions

Wave-plasma

interaction

Fusion-reaction

crosssection

ā€¢ Both ICRF waves and fusion reaction generate energetic ions andare affected by the energetic ions.

ā€¢ In the start up phase of ITER plasmas, the role of ICRF waves isimportant, time-evolving, and sensitive to the plasma conditions

Page 3: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Introduction(2)

Gyrokinetic Behavior of Energetic Ions

ICRF wavesEnergetic

ions

Non-Maxwellian

velocity distribution

Large orbit size

ā€¢ Self-consistent analysis of non-Maxwellian velocity distribution func-tion is necessary.

ā€¢ Finite gyroradius and finite orbit size affect the behavior of ICRFwaves.

Page 4: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Introduction(3)

Comprehensive Modeling of Burning Plasmas

ICRF wavesEnergetic

ions

AlfvƩn Eigenmode

Transport

Orbit loss

Bulk plasma

ā€¢ Energetic ions interact with bulk plasmas through, for example, trans-port processes and orbit loss.

ā€¢ Alfven eigenmodes may affect the energetic ions themselves.

ā€¢ Integrated comprehensive modeling of burning plasmas is inevitable.

Page 5: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Introduction (4)

ā€¢ Analysis of ICRF waves in burning plasma requires

ā—¦ Full wave analysis

ā—¦ Non-Maxwellian velocity distribution function

ā—¦ Finite gyroradius effect

ā—¦ Integrated modeling

ā€¢ Integrated approach using the TASK code

Page 6: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

TASK Code

ā€¢ Transport Analysing System for TokamaK

ā€¢ Features

ā—¦ A Core of Integrated Modeling Code in BPSIā€” Modular structure, Unified Standard data interfaceā—¦ Various Heating and Current Drive Schemeā€” Full wave analysis for IC and AWā€” Ray and beam tracing for EC and LHā€” 3D Fokker-Planck analysisā—¦ High Portabilityā—¦ Development using CVSā—¦ Open Sourceā—¦ Parallel Processing using MPI Libraryā—¦ Extension to Toroidal Helical Plasmas

Page 7: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Modules of TASK

PL Data Interface Data conversion, Profile databaseEQ 2D Equilibrium Fixed/Free boundary, Toroidal rotationTR 1D Transport Diffusive transport, Transport models

WR 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)LIB Libraries LIB, MTX, MPI

Under DevelopmentTX Transport analysis including plasma rotation and ErEG Gyrokinetic linear stability analysis

Imported from TOPICSEQU Free boundary equilibriumNBI NBI heating

Page 8: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Modular Structure of TASK

EQ

T R

PL

W R

DP

F ixed-boundary equilibrium

Diffusive transport

IT PAļæ½ļæ½ļæ½ ļæ½ļæ½ļæ½

le DB

JT -6 0 Exp. Data

Experimental

Database

Simulation DB

T X

F P

W M

W X

Dynamic transport

Kinetic transport

Ray tracing

F ull wave analysis

F ull wave analysis including F LR

Dispersion relation

EG Gyrokinetic linear microinstabilities

EQU

NBI

T O PIC S/ F ree-boundary equilibrium

T O PIC S/ Neutral beam injection

Data

Interface

Page 9: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Inter-Module Collaboration Interface: TASK/PL

ā€¢ Role of Module Interface

ā—¦ Data exchange between modules:ā€” Standard dataset: Specify set of data (cf. ITPA profile DB)ā€” Specification of data exchange interface: initialize, set, getā—¦ Execution control:ā€” Specification of execution control interface:

initialize, setup, exec, visualize, terminateā€” Uniform user interface: parameter input, graphic output

ā€¢ Role of data exchange interface: TASK/PL

ā—¦ Keep present status of plasma and deviceā—¦ Store history of plasmaā—¦ Save into file and load from fileā—¦ Interface to experimental data base

Page 10: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

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 Īŗ Elongation at boundaryRDLT Ī“ Triangularity at boundaryRIP Ip A Typical plasma current

Equilibrium data: (Level 1)PSI2D Ļˆp(R,Z) Tm2 2D poloidal magnetic fluxPSIT Ļˆt(Ļ) Tm2 Toroidal magnetic fluxPSIP Ļˆp(Ļ) Tm2 Poloidal magnetic fluxITPSI It(Ļ) Tm Poloidal current: 2Ļ€BĻ†RIPPSI Ip(Ļ) Tm Toroidal currentPPSI p(Ļ) MPa Plasma pressureQINV 1/q(Ļ) Inverse of safety factor

Metric data1D: V ā€²(Ļ), 怈āˆ‡V怉(Ļ), Ā· Ā· Ā·2D: gi j, Ā· Ā· Ā·3D: gi j, Ā· Ā· Ā·

Fluid plasma dataNSMAX s Number of particle speciesPA As Atomic massPZ0 Z0s Charge numberPZ Zs Charge state numberPN ns(Ļ) m3 Number densityPT Ts(Ļ) eV TemperaturePU usĻ†(Ļ) m/s Toroidal rotation velocityQINV 1/q(Ļ) Inverse of safety factor

Kinetic plasma dataFP f (p, Īøp, Ļ) momentum dist. fn at Īø = 0

Dielectric tensor dataCEPS ā†”Īµ (Ļ, Ļ‡, Ī¶) Local dielectric tensor

Full wave field dataCE E(Ļ, Ļ‡, Ī¶) V/m Complex wave electric fieldCB B(Ļ, Ļ‡, Ī¶) 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 Ļ†(`) rad Ļ† 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 `

Page 11: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Example: Data Structure and Program Interface

ā€¢ Data structure: Derived type (Fortran95)

type bpsd_plasmaf_data

real(8) :: pn ! Number density [mĖ†-3]

real(8) :: pt ! Temperature [eV]

real(8) :: ptpr ! Parallel temperature [eV]

real(8) :: ptpp ! Perpendicular temperature [eV]

real(8) :: pu ! Parallel flow velocity [m/s]

end type bpsd_plasmaf_data

type bpsd_plasmaf_type

real(8) :: time

integer :: nrmax ! Number of radial points

integer :: nsmax ! Number of particle species

real(8), dimension(:), allocatable :: s

! (rhoĖ†2) : normarized toroidal flux

real(8), dimension(:), allocatable :: qinv

! 1/q : inverse of safety factor

type(bpsd_plasmaf_data), dimension(:,:), allocatable :: data

end type bpsd_plasmaf_type

ā€¢ Program interface

Set data bpsd set data(plasmaf,ierr)

Get data bpsd get data(plasmaf,ierr)

Save data bpsd save data(filename,plasmaf,ierr)Load data bpsd load data(filename,plasmaf,ierr)Plot data bpsd plot data(plasmaf,ierr)

Page 12: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Examples of sequence in a module

ā€¢ TR EXEC(dt)

call bpsd get data(plasmaf,ierr)

call bpsd get data(metric1D,ierr)

local data <- plasmaf,metric1D

advance time step dt

plasmaf <- local data

call bpsd set data(plasmaf,ierr)

ā€¢ EQ CALC

call bpsd get data(plasmaf,ierr)

local data <- plasmaf

calculate equilibrium

update plasmaf

call bpsd set data(plasmaf,ierr)

equ1D,metric1D <- local data

call bpsd set data(equ1D,ierr)

call bpsd set data(metric1D,ierr)

Page 13: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Wave Dispersion Analysis : TASK/DP

ā€¢ Various Models of Dielectric Tensorā†”Īµ (Ļ‰, k; r):ā—¦ Resistive MHD modelā—¦ Collisional cold plasma modelā—¦ Collisional warm plasma modelā—¦ Kinetic plasma model (Maxwellian, non-relativistic)ā—¦ Kinetic plasma model (Arbitrary f (u), relativistic)ā—¦ Gyro-kinetic plasma model (Maxwellian)

ā€¢ Numerical Integration in momentum space: Arbitrary f (u)ā—¦ Relativistic Maxwellianā—¦ Output of TASK/FP: Fokker-Planck code

Page 14: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Full wave analysis: TASK/WM

ā€¢magnetic surface coordinate: (Ļˆ, Īø, Ļ•)

ā€¢ Boundary-value problem of Maxwellā€™s equation

āˆ‡ Ɨ āˆ‡ Ɨ E =Ļ‰2

c2ā†”Īµ Ā· E + iĻ‰Āµ0 jext

ā€¢ Kinetic dielectric tensor: ā†”Īµā—¦Wave-particle resonance: Z[(Ļ‰ āˆ’ nĻ‰c)/kā€–vth]ā—¦ Finite gyroradius effect: Reductive =ā‡’ Integral (ongoing)

ā€¢ Poloidal and toroidal mode expansion

ā€¢ FDM: =ā‡’ FEM (onging)

ā€¢ Eigenmode analysis: Complex eigen frequency which maximizewave amplitude for fixed excitation proportional to electron density

Page 15: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Fokker-Planck Analysis : TASK/FP

ā€¢ Fokker-Planck equationfor velocity distribution function f (pā€–, pāŠ„, Ļˆ, t)

āˆ‚ fāˆ‚t= E( f ) +C( f ) + Q( f ) + L( f )

ā—¦ E( f ): Acceleration term due to DC electric fieldā—¦ C( f ): Coulomb collision termā—¦ Q( f ): Quasi-linear term due to wave-particle resonanceā—¦ L( f ): Spatial diffusion term

ā€¢ Bounce-averaged: Trapped particle effect, zero banana width

ā€¢ Relativistic: momentum p, weakly relativistic collision term

ā€¢ Nonlinear collision: momentum or energy conservation

ā€¢ Three-dimensional: spatial diffusion (neoclassical, turbulent)

Page 16: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Self-Consistent Wave Analysis with Modified f (u)

ā€¢Modification of velocity distribution from Maxwellian

ā—¦ Energetic ions generated by ICRF wavesā—¦ Alpha particles generated by fusion reactionā—¦ Fast ions generated by NB injection

ā€¢ Self-consistent wave analysis including modification of f (u)

Page 17: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Preliminary Results

ā€¢ Tail formation by ICRF minority heating

Wave pattern

Quasi-linear Diffusion Momentum Distribution

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

2

4

6

8

10

PPARA

PPERP

DWPP FMIN = 0.0000E+00 FMAX = 5.7337E+01 STEP = 2.5000E+00

-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

Tail Formation Power deposition

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

Page 18: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Finite Gyroradius Effects in Full Waves Analyses

ā€¢ Several approaches to describe the finite gyroradius effects.

ā€¢ Differential operators: kāŠ„Ļā†’ iĻāˆ‚/āˆ‚rāŠ„ā—¦ This approach cannot be applied to the case kāŠ„Ļ & 1.ā—¦ Extension to the third and higher harmonics is difficult.

ā€¢ Spectral method: Fourier transform in inhomogeneous direction

ā—¦ This approach can be applied to the case kāŠ„Ļ > 1.ā—¦ All the wave field spectra are coupled with each other.ā—¦ Solving a dense matrix equation requires large computer resources.

ā€¢ Integral operators:āˆ«Īµ(x āˆ’ xā€²) Ā· E(xā€²)dxā€²

ā—¦ This approach can be applied to the case kāŠ„Ļ > 1ā—¦ Correlations are localized within several gyroradiiā—¦ Necessary to solve a large band matrix

Page 19: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Full Wave AnalysisUsing an Integral Form of Dielectric Tensor

ā€¢Maxwellā€™s equation:

āˆ‡ Ɨ āˆ‡ Ɨ E(r) +Ļ‰2

c2

āˆ«ā†”Īµ (r, rā€²) Ā· E(rā€²)dr = Āµ0 jext(r)

ā€¢ Integral form of dielectric tensor: ā†”Īµ (r, rā€²)ā—¦ Integration along the unperturbed cy-

clotron orbit

ā€¢ 1D analysis in tokamaks

ā—¦ To confirm the applicability

ā—¦ Similar formulation in the lowest orderof Ļ/L

ā€” Sauter O, Vaclavik J, Nucl. Fusion 32(1992) 1455.

s'

t'

t

s0 s

ļæ½p

v

Page 20: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

One-Dimensional Analysis (1)

ICRF minoring heating without energetic particles (nH/nD = 0.1)

Differential form Integral form[V/m]

Ex

Ey

[W/m2]

PH

PDPe

[V/m]

Ex

Ey

PH

Pe PD

[W/m2]

R0 = 1.31m

a = 0.35m

B0 = 1.4T

Te0 = 1.5keV

TD0 = 1.5keV

TH0 = 1.5keV

ns0 = 1020māˆ’3

Ļ‰/2Ļ€ = 20MHz

Differential approach is applicable

Page 21: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

One-Dimensional Analysis (2)

ICRF minoring heating with energetic particles (nH/nD = 0.1)

Differential form Integral form[V/m]

Ex

Ey

[W/m2]

Pe

PH

PD

[V/m]

Ex

Ey

[W/m2]

PH

Pe

PD

R0 = 1.31m

a = 0.35m

B0 = 1.4T

Te0 = 1keV

TD0 = 1keV

TH0 = 100keV

ns0 = 1020māˆ’3

Ļ‰/2Ļ€ = 20MHz

Differential approach cannot be applied since kāŠ„Ļi > 1.

Page 22: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

One-Dimensional Analysis (3)

ICRF minoring heating with Ī±-particles (nD : nHe = 0.96 : 0.02)Differential form Integral form

[V/m]

Ex

Ey

[W/m 2]

PePD

PHe

[V/m]

Ex

Ey

[W/m 2]

PD

PHe

Pe

R0 = 3.0m

a = 1.2m

B0 = 3T

Te0 = 10keV

TD0 = 10keV

TĪ±0 = 3.5MeV

ns0 = 1020māˆ’3

Ļ‰/2Ļ€ = 45MHz

Absorption by Ī± may be over- or under-estimated by differentialapproach.

Page 23: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

3D Formulation

ā€¢ Coordinates

ā—¦Magnetic coordinate system: (Ļˆ, Ļ‡, Ī¶)ā—¦ Local Cartesian coordinate system: (s, p, b)ā—¦ Fourier expansion: poloidal and toroidal mode numbers, m, n

ā€¢ Perturbed current

j(r, t) = āˆ’ qm

āˆ«du qu

āˆ« āˆžāˆ’āˆž

dtā€²[E(rā€², tā€²) + uā€² Ɨ B(rā€², tā€²)

]Ā· āˆ‚ f0(uā€²)

āˆ‚uā€²

ā€¢Maxwell distribution functionā—¦ Anisotropic Maxwell distribution with TāŠ„ and Tā€– :

f0(s0, u) = n0

(m

2Ļ€TāŠ„

)3/2 (TāŠ„Tā€–

)1/2

exp

[āˆ’ v2

āŠ„2v2

TāŠ„

āˆ’v2ā€–

2v2Tā€–

]

Page 24: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Variable Transformations

ā€¢ Transformation of Integral Variables

ā—¦ Transformation from the velocity spacevariables (vāŠ„, Īø0) to the particle positionsā€² and the guiding center position s0.

ā—¦ Jacobian: J =āˆ‚(vāŠ„, Īø0)āˆ‚(sā€², s0)

= āˆ’ Ļ‰2c

vāŠ„ sinĻ‰cĻ„.

s'

t'

t

s0 s

ļæ½p

v

ā—¦ Express vāŠ„ and Īø0 by sā€² and s0 using Ļ„ = t āˆ’ tā€², e.g.,

vāŠ„ sin(Ļ‰cĻ„ + Īø0) =Ļ‰c

vāŠ„

s āˆ’ sā€²

21

tan 12Ļ‰cĻ„

+Ļ‰c

vāŠ„

(s + sā€²

2āˆ’ s0

)tan

12Ļ‰cĻ„

ā€¢ Integration over Ļ„: Fourier expansion with cyclotron motion

ā€¢ Integration over vā€–: Plasma dispersion function

Page 25: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Final Form of Induced Current

ā€¢ Induced current:

Ā·

Jmns (s)

Jmnp (s)

Jmnb (s)

= āˆ«dsā€²

āˆ‘mā€²nā€²

ā†”Ļƒmā€²nā€²mn(s, sā€²) Ā·

Emā€²nā€²s (sā€²)

Emā€²nā€²p (sā€²)

Emā€²nā€²b (sā€²)

ā€¢ Electrical conductivity:

ā†”Ļƒmā€²nā€²mn(s, sā€²) = āˆ’in0q2

m

āˆ‘`

āˆ«ds0

āˆ« 2Ļ€

0dĻ‡0

āˆ« 2Ļ€

0dĪ¶0 exp i

{(mā€² āˆ’ m)Ļ‡0 + (nā€² āˆ’ n)Ī¶0

} ā†”H `(s, sā€², s0, Ļ‡0, Ī¶0)

ā€¢Matrix coefficients:ā†”H `(s, sā€², s0, Ļ‡0, Ī¶0)

ā—¦ Four kinds of Kernel functions including s, sā€², s0 and harmonicsnumber `

ā€” The kernel functions are localized within several thermal gyro-radii.

ā—¦ Plasma dispersion function

Page 26: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Kernel Functions

ā€¢ Kernel Function and its integrals

F(100)0 F(100)

1

Page 27: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Status of extension to 3D configuration

ā€¢ In a homogeneous plasma, usual formula including th Bessel func-tions can be recovered.

ā€¢ Kernel functions are the same as the 1D case,

ā€¢ FEM formulation is required for convolution integral.

ā€¢ Development of the FEM version of TASK/WM is ongoing (al-most complete).

ā€¢ Integral operator code in 3D configuration is waiting for the FEMversion of TASK/WM.

Page 28: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Consistent Formulation of Integral Full Wave Analysis

ā€¢ Full wave analysis for arbitrary velocity distribution functionā—¦ Dielectric tensor:

āˆ‡ Ɨ āˆ‡ Ɨ E(r) āˆ’ Ļ‰2

c2

āˆ«dr0

āˆ«drā€²

pā€²

mĪ³āˆ‚ f0(pā€², r0)

āˆ‚pā€²Ā· K1(r, rā€², r0) Ā· E(rā€²) = iĻ‰Āµ0 jext

where r0 is the gyrocenter position.

ā€¢ Fokker-Planck analysis including finite gyroradius effectsā—¦ Quasi-linear operatorāˆ‚ f0āˆ‚t+

(āˆ‚ f0āˆ‚p

)E+āˆ‚

āˆ‚p

āˆ«dr

āˆ«drā€²E(r) E(rā€²) Ā·K2(r, rā€², r0) Ā· āˆ‚ f0(pā€², r0, t)

āˆ‚pā€²=

(āˆ‚ f0āˆ‚p

)col

ā€¢ The kernels K1 and K2 are closely related and localized in the re-gion |r āˆ’ r0| . Ļ and |rā€² āˆ’ r0| . Ļ.

ā€¢ To be challenged

Page 29: Integrated Full-Wave Modeling of ICRF Heating in Tokamak

Summary

ā€¢ Comprehensive analyses of ICRF heating in tokama plasmas

ā—¦ Time-evolution of the velocity distribution functions and the finitegyroradius effects have to be consistently included. For this pur-pose, the extension of the integrated code TASK is ongoing.

ā€¢ Self-consistent analysis including modification of f (p)ā—¦ Full wave analysis with arbitrary velocity distribution function and

Fokker-Planck analysis using full wave field are available. Pre-liminary result of self-consistent analysis was obtained.

ā€¢ 3D full wave analysis including the finite gyroradius effects:

ā—¦ 1D analysis elucidated the importance of the gyroradius effectsof energetic ions. Formulation was extended to a 2D configura-tion. Implementation is waiting for the FEM version of TASK/WM.