common description of dina code

ASIPPASIPP , , MarchMarch 19,19, 20 201212 11

Using of DINA code in Using of DINA code in tokamak plasma modeling tokamak plasma modeling

V. Lukash (V. Lukash (NRC Kurchatov Institute, Moscow, RussiaNRC Kurchatov Institute, Moscow, Russia), ), R. Khayrutdinov (R. Khayrutdinov (TRINITI, Troitsk, RussiaTRINITI, Troitsk, Russia),),

V. Dokuka (V. Dokuka (TRINITI, Troitsk, RussiaTRINITI, Troitsk, Russia))

Common description of DINADINA code DINA is a 1.5-D axisymmetric, time-dependent, transport-modeling,

free boundary in external magnetic field tokamak plasma simulation code

Circuit equations are solved for PF coil currents, vacuum vessel and passive structure eddy currents self-consistently with plasma equilibrium

DINA code includes neutral beam and RF heating, impurity radiation model, pellet injection, runaway electrons, mixing and halo-currents models, bootstrap, current drive, particles heating, module for breakdown and null field formation

Code has equilibrium reconstruction module with taking into account vessel current and halo currents

Khayrutdinov and Lukash. Journal of Comp. Physics, v.109 (1993) 193

Lukash and Khayrutdinov. Plasma Physics Reports, v.22 (1996) p. 99


DINADINA for plasma scenario control and

disruptions • Validation against TCV, JT-60U, GLOBUS-M, ASDEX-U, MAST, DIII-D plasma control experiments

• DINADINA is officialofficial code for ITER plasma position, shape and current control including plasma initiation stage with taking into account power supply limitations and disruption modeling

• MATLAB version of DINA-CH

• DINADINA is installed

>> DIII-D (control & disruptions)

>> TCV (control)

>> ASDEX-U (disruptions)

>> MAST (control & disruptions)

>> Kyoto University (Japan, disruptions)

>> JT-60 SA team (Japan, disruptions)

>> ITER organization (control & disruption)

DINA in DINA in TCVTCV

Khayrutdinov, Lukash, Comput. Physics, 109 (1993) 193

33ASIPPASIPP , , MarchMarch 19,19, 20 201212

DINA-CHDINA-CH Matlab-SimulinkMatlab-Simulink

44

J.B. Lister, et al. Fusion Eng. And Design 74 (2005) 633

ASIPPASIPP , , MarchMarch 19,19, 20 201212

DINA-CHDINA-CH is coupled with CRONOS CRONOS code


S.H. Kim et al. , PPCF 51 (2009) 105007

DINA

CONTROLSYSTEM

66

DINADINA modeling modeling of ITER plasma of ITER plasma current, shape current, shape and position and position controlcontrol


Simulation of ITER plasma scenarios starting from initial discharge of central solenoid

Fist plasma equilibrium simulated with the DINA code

(0.1MA)

0

0,5

1

1,5

2

2,5

3

3,5

160

165

170

175

180

185

190

195

1,5 2 2,5 3 3,5 4 4,5 5

time, s

a, cm

Ip, MA

li(3)

Te, keV

phase 1 phase 2

phase 3 phase 4

Zeff

Plasma current, average electron temperature, Zeff and li(3) during first 5 s

after breakdown

Resistances of the switching network units and waveforms of the feedforward (pre-programmed) voltages in all CS and PF coils from 0 to 1.5 s are taken from the corresponding TRANSMAKTRANSMAK simulation

LukashLukash 38th EPS38th EPS 20112011



Submitted to 39th EPS 2012

DINADINA “real time control” of ITER scenario

1010

R.R. Khayrutdinov 34th EPS 2007



Reconstructed plasma


R.R. KhayrutdinovR.R. Khayrutdinov 34th EPS34th EPS 20072007


2530354045

505560

Z, cm

time, s

twst

d-l

580

600

620

640

660

680

700R, cm

without reconstructionwith reconstruction50s wrong signals

0

5

10

15Ip, MA

0 20 40 60 80 100 120 140

time, s


R.R. KhayrutdinovR.R. Khayrutdinov 34th EPS34th EPS 20072007

Disruption simulations (Integrated simulator DINA DINA and and ZIMPURZIMPUR)

DINA -ZIMPURDINA -ZIMPUR integrating integrating codecode

ZIMPURZIMPUR – impurity – impurity radiation and transport. radiation and transport. Multi energy group Multi energy group kinetics for neutralskinetics for neutrals

Halo currents evolution Halo currents evolution ((DINADINA))

RE Rothenbluth – RE Rothenbluth – Putvinski; axially Putvinski; axially symmetrical heat loadssymmetrical heat loads

Simulations of RE in DINA

1313

V.E. LukashV.E. Lukash Nuclear Fusion 47 (2007) 1476Nuclear Fusion 47 (2007) 1476


Halo model in DINADINA code

z

r

Limited core plasma together with halo

area

Ip during disruption

halotorIR

E

2

Plasma is shrinking in limiter phase

halopolhlp IRIdleE

2

1

Halo width definition in DINA code

Lukash, KhayrutdinovLukash, Khayrutdinov PPR 1996PPR 1996

bm

sbtw)(


11

1),(

),( 0

0

CI

wtIC

wtS

S

p

p

Halo width scaling in Halo width scaling in DINADINA

DINADINA modeling of halo inmodeling of halo in ASDEX-ASDEX-UU during disruptionduring disruption

100 120 140 160 180 200 220

-120

-100

-80

-60

-40

-20

0

20

40

ASDEX-U #25000; t=3133 ms

r [cm]

z [c

m]

100 120 140 160 180 200 220

-120

-100

-80

-60

-40

-20

0

20

40

ASDEX-U #25000; t=3135 ms

r [cm]

z [c

m]

100 120 140 160 180 200 220

-120

-100

-80

-60

-40

-20

0

20

ASDEX-U #25000; t=3137 ms

r [cm]

z [c

m]

1515

G. Pautasso et al. NF 51 (2011) G. Pautasso et al. NF 51 (2011) 103009103009


DINADINA predictive analysis of ASDEX disruptive plasma

0

50

100

150

200

250

300

3,07 3,075 3,08 3,085 3,09

t, s

Ih pol

, kA

IDINA tot

IDINA

Iexp

ASDEX-U #24999 (a)

0

50

100

150

200

250

300

350

3,125 3,13 3,135 3,14

ASDEX-U #25000 (b)

t, s

Ih pol

, kA

IDINA tot

IDINA

Iexp

G. Pautasso et al. NF 51 (2011) G. Pautasso et al. NF 51 (2011) 103009103009


Fitting mode of DINADINA code

Minimizing of difference between calculated and measured Вp and l gives information about:Boundary of the core plasma b

Boundary of the halo area s = b – w (m - b)

Plasma current profile

(n=05) Current distribution in vacuum vessel

filaments Ives =I0+Amcos(m)+Bm sin(m) (m=15) Error value 2 minimization results: b, s, an, bn, Am, Bm, w

Magnetic diagnostics in ASDEX-U

2222PFprobesloops

RRnnbRRnnatj /0)(0/)(

M. Sugihara, V. Lukash et al. PPCF (2004) 1581


DINADINA fitting analysis of JT-60U disruptive plasma H. Tamai et al. NF 42 (2002) H. Tamai et al. NF 42 (2002)

290290


MAST Halo Current DINADINA SimulationsM.J. Windridge et al. 34M.J. Windridge et al. 34thth EPS EPS

(2007) (2007)


Database of VDE and MD scenarios in ITER plasma is being carried out with DINADINA

M. Sugihara, et al. NF 47 (2007) 1581


Plasma opacity taking into account during disruption in ITER

plasma

0

5

10

15

20

C, 9*1019m-3w/o opacityw opacity

I, MA

Ip

Ih tor

0

0.5

1

1.5

2

Ira

, MA

0

10

20

30

40

50

60

5 10 15 20 25 30t, ms

Te, eV

V. Lukash, et al. NF 47 (2007) 1476


Evolution of ITER plasma parameters with Li and Be pellet injection

0

2

4

6

8

10

12

14

16

0 20 40 60 80 100

time, ms

I, MA

Ip

IreLi - 7.5 g

18 g 35 g

Be - 1 g 2 g 3.2 g 8 g

V. Lukash, et al. 23nd IAEA FEC (2010) THD/P2-01


DINADINA simulation of disruption in ITER simulation of disruption in ITER plasmaplasma


SOL-DINASOL-DINA Modelling of Li limiter Experiments in T-11M tokamak

Numerical results arecompared with theexperimental lithiumdistribution in a SOL determined by means

of (Li I=670,8 nm)spectral line intensitymeasurement on themoving C-limitersurface as a functionof its position

Lukash, et al. 22nd IAEA FEC (2008) TH/P4-12


What is meant by version DINA-DINA-EASTEAST

DINA-EAST code version is intended to model the uncontrollable tokamak plasma evolution during a VDE and has to include a module for the calculation of halo currents. This version includes both fittingfitting and predictivepredictive simulation modes.

The fitting mode is being used to calculate an initial equilibrium and to reconstruct the plasma equilibria during the fitting mode time period.

The predictive mode is being used just after the fitting mode switching off. In predictive mode there is a possibility to define the waveform of average plasma electron temperature either from input file or by means of artificial feedback to reproduce an experimental plasma current behavior


Plan of DINADINA setup for EASTEAST tokamak

Implementation of EAST geometry, electrical properties of the conductors (coils, vessels, in vessel components), magnetic diagnostic geometry into the DINA code

Testing of the EAST experimental EM responses without plasma

Development of interface between the EAST experimental magnetic data and DINA code for fitting mode modelling. Validation of DINA fitting mode against the EAST experimental data

Validation of the DINA predictive mode against the VDE shots in EAST plasma (increment of vertical movement)

Validation of DINA code against the disruption shots in EAST plasma with the halo currents modelling. Comparison with experimental data


Conclusion 1.5-D axisymmetric, time-dependent, free boundary

equilibrium and transport-modeling tokamak plasma evolution DINADINA code is used for magnetic control, scenario and disruption simulations

DINADINA code has been validated in GLOBUS, T11-M, DIII-D, TCV, ASDEX-U, JT-60U and MAST tokamaks

DINADINA code has been used in KTM design studies

DINADINA is official code for ITER plasma position, shape and current control including plasma initiation stage with taking into account power supply limitations and disruption modeling

DINADINA is going to be used for analysis of disruptive EASTEAST plasma shots in both fitting and predictive modes


common description of dina code

Documents

ch dina

plasma scenario control

current control

position control asipp

iter plasma position

tokamak plasma modeling

ma plasma current

plasma equilibriumdina