common description of dina code
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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
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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
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DINA-CHDINA-CH is coupled with CRONOS CRONOS code
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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
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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
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88ASIPPASIPP , , MarchMarch 19,19, 20 201212
Submitted to 39th EPS 2012
99ASIPPASIPP , , MarchMarch 19,19, 20 201212
Submitted to 39th EPS 2012
DINADINA “real time control” of ITER scenario
1010
R.R. Khayrutdinov 34th EPS 2007
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DINADINA “real time control” of ITER scenario
Reconstructed plasma
1111ASIPPASIPP , , MarchMarch 19,19, 20 201212
R.R. KhayrutdinovR.R. Khayrutdinov 34th EPS34th EPS 20072007
DINADINA “real time control” of ITER scenario
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
1212ASIPPASIPP , , MarchMarch 19,19, 20 201212
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
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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)(
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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
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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
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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
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DINADINA fitting analysis of JT-60U disruptive plasma H. Tamai et al. NF 42 (2002) H. Tamai et al. NF 42 (2002)
290290
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MAST Halo Current DINADINA SimulationsM.J. Windridge et al. 34M.J. Windridge et al. 34thth EPS EPS
(2007) (2007)
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Database of VDE and MD scenarios in ITER plasma is being carried out with DINADINA
M. Sugihara, et al. NF 47 (2007) 1581
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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
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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
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DINADINA simulation of disruption in ITER simulation of disruption in ITER plasmaplasma
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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
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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
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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
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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
ASIPPASIPP , , MarchMarch 19,19, 20 201212 2727
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