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OPERATIONAL SCENARIO of KTM Dokuka V.N., Khayrutdinov R.R. TRINITI, Russia. O u t l i n e Goal of the work The DINA code capabilities Formulation of the problem Examples of simulations Conclusions Future work. Goal of the work. Modeling of different discharge scenarios for KTM tokamak

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operational scenario of ktm dokuka v n khayrutdinov r r triniti russia
OPERATIONAL SCENARIO of KTMDokuka V.N., Khayrutdinov R.R.TRINITI, Russia

O u t l i n e

  • Goal of the work
  • The DINA code capabilities
  • Formulation of the problem
  • Examples of simulations
  • Conclusions
  • Future work
slide2

Goal of the work

  • Modeling of different discharge scenarios for KTM tokamak
  • Optimization of Ramp-up processes
  • Development of PF currents waveforms for ramp-up and flat-top and shut-down cases
  • Study OH and ICRF heating regimes with different heat conductivity scaling-laws
  • Plasma vertical position stabilization control
  • Disruptions simulation
  • X-point position control
equilibrium and transport modeling code dina
Equilibrium and transport modeling code DINA

DINA is Free Boundary Resistive MHD and Transport-Modeling Plasma Simulation Code

The following problems for plasma can be solved:

  • Plasma position and shape control;
  • Current ramp up and shut down simulations;
  • Scenarios of heating, fuelling, burn and non-inductive current drive;
  • Disruption and VDE simulations (time evolution, halo currents and run away electron effects);
  • Plasma equilibrium reconstruction;
  • Simulation of experiments in fitting mode using experimental magnetic and PF measurements
  • Modeling of plasma initiation and dynamic null formation.
dina code applications
DINA code applications
  • DINA code has been benchmarked with PET, ASTRA and TSC codes. Equilibrium part was verified to the EFIT code
  • Control, shaping, equilibrium evolution have been validated against DIII-D, TCV and JT-60 experimental data
  • Disruptions have been studied at DIII-D, JT-60, Asdex-U and COMPASS-D devices
  • Breakdown study at NSTX and plasma ramp-up at JT-60 and DIII-D
  • Discharge simulations at FTU, GLOBUS and T11 tokamaks
  • Selection of plasma parameters for ITER, IGNITOR,KTM and KSTAR projects
  • Modeling of plasma shape and position control for MAST, TCV and DIII-D
theoretical and numerical analysis of plasma physical processes at ktm
Theoretical and numerical analysis of plasma-physical processes at KTM
  • Breakdown and plasma initiation
  • Ramp-up
  • Flat-top
  • Plasma Vertical Stability
  • Disruptions
  • Shot down
slide6

Scheme of discharge scenario at KTM

Bt = 1 T

IP = 0.75 MA

Paux = 5 MW

Plasma current flat-top

Plasma current shut-down

Plasma current ramp-up

Auxiliary heating

Toroidal magnetic field creation

Plasma current initiation

Vacuum creation, gas puff

the previous ktm scenario 2

The previous KTM scenario (2)

Plasma current current density, boundary and equilibrium during ramp-up

ramp up 1
Ramp-up (1)
  • Results of plasma initiation calculation are inputs for ramp-up simulation ( values of PF coil and vessel and total plasma currents, plasma current density)
  • Set of snapshot calculations are used to choose waveforms for PF coil and plasma current and for plasma boundary ;
  • Transition from limited to X-point plasma is carefully modeled;
  • Optimization of Volt-second consumption of inductor-solenoid is carried out;
  • Ramp-up time ( speed of ramp-up) is optimized to avoid “skin currents” at plasma boundary;
  • Pf coil currents and density waveforms are carefully programmed to avoid plasma instability and runaway current
techniques used for creation pf scenario
Techniques used for creation PF scenario
  • Dina calculates plasma equilibrium with programmed PF currents
  • Programmed parameters are plasma density, plasma current, auxiliary heating power
  • To simulate plasma evolution one must use a controller. Today it is absent
  • We had to apply DINA means for controlling plasma current by using CS current, and to control R-Z position by using PF3 and HFC currents respectively
  • How to create PF programmed set:
  • The initial PF data was obtained in the end of stage of plasma initiation
  • At first the plasma configurations at the end of ramp up stage and for flat top are calculated
programmed inputs for dina
Programmed inputs for DINA

n(t)

P(t)

DINA

Ip(t)

PF(t)

PF(t)

techniques used for creation pf scenario continue
Techniques used for creation PF scenario (continue)
  • Having used such a programmed PF currents, we find out that plasma configuration becomes wrong from some moment. To stop simulation at this moment! To write required information for fulfilling the next step
  • To calculate a static desired plasma configuration by taking into account information concerning plasma current profile and vacuum vessel filaments currents obtained at some previous moment
  • A new PF currents should be included in PF programmed set
  • To carry out simulation up to this moment.
  • To repeat procedure of improving PF current data for achieving good agreement
  • To continue simulation further
a set of initial snapshot calculations
A set of initial snapshot calculations

time= 9 ms

time= 279 ms

time= 499 ms

time= 3999 ms

ramp up initial equilibrium
Ramp –up (initial equilibrium)

Plasma equilibrium during ramp-up

slide15

Equilibrium at the end of ramp-up

Plasma equilibrium during ramp-up

ramp up profiles
Ramp –up (profiles)
  • Plasma current density profiles
  • Safety factor profiles
  • Electron temperature profiles
  • Bootstrap current profiles
flat top
Flat-top
  • Set of snapshot calculations are used to choose waveforms for PF coil and plasma current and for plasma boundary ;
  • Optimization of Volt-second consumption of inductor-solenoid is carried out for Ohmic and Auxiliary Heating scenarios
  • Different scaling-laws for heat conductivity ( Neo-Alcator, T-11, ITER-98py ) are used
  • Different profiles of auxiliary heating deposition can be applied
  • Optimization of scenario to avoid MHD instabilities
  • X-point swiping to minimize thermal load at divertor
flat top typical configuration
Flat-top (typical configuration)

Plasma equilibrium during flat-top

evolution of plasma parameters 1
Evolution of plasma parameters 1
  • Plasma current
  • Poloidal beta
  • Minor radius
  • Horizontal magnetic axis
evolution of plasma parameters 2
Evolution of plasma parameters 2
  • Averaged electron density
  • Elongation
  • Internal inductance
  • Vacuum vessel current
evolution of plasma parameters 3
Evolution of plasma parameters 3
  • Averaged ion temperature
  • Safety factor on magnetic axis
  • Safety factor on the plasma boundary
  • Averaged electron temperature
evolution of plasma parameters 4
Evolution of plasma parameters 4
  • Electron density in the plasma center
  • Global confinement time
  • Major plasma radius
  • Resistive loop voltage
evolution of plasma parameters 5
Evolution of plasma parameters 5
  • Vertical position of magnetic axis
  • Bootstrap current
  • beta
  • Normalized beta
evolution of plasma parameters 6
Evolution of plasma parameters 6
  • Ion temperature on magnetic axis
  • Auxiliary heating (ICRH)
  • Electron temperature on magnetic axis
  • Resistive loop Volt-seconds
evolution of plasma parameters 7
Evolution of plasma parameters 7
  • Total Volt-seconds
  • Plasma Volt-seconds
  • External Volt-seconds
  • Ion confinement time
evolution of plasma parameters 8
Evolution of plasma parameters 8
  • Ion confinement time
  • Volt-seconds of PF (without CS)
  • Volt-seconds of CS
  • Ohmic heating power
evolution of plasma parameters 9
Evolution of plasma parameters 9
  • Minor radius (95%)
  • Upper elongation (95%)
  • Down elongation (95%)
  • Elongation (95%)
evolution of plasma parameters 10
Evolution of plasma parameters 10
  • Upper triangularity (95%)
  • Down triangularity (95%)
  • Triangularity (95%)
  • Horizontal position of magnetic axis
evolution of plasma parameters 11
Evolution of plasma parameters 11
  • Z-coordinate of X-point
  • Current in upper passive plate
  • Current in lower passive plate
  • R-coordinate of X-point
flat top profiles 1
Flat-top (profiles - 1)
  • Plasma current density profiles
  • Safety factor profiles
  • Electron temperature profiles
  • Bootstrap current profiles
flat top profiles 2
Flat-top (profiles –2 )
  • Plasma current density profiles
  • Safety factor profiles
  • Electron temperature profiles
  • Bootstrap current profiles
flat top profiles 3
Flat-top (profiles –3)
  • Plasma current density profiles
  • Safety factor profiles
  • Electron temperature profiles
  • Bootstrap current profiles
conclusions
Conclusions
  • The creation of scenario for KTM including ramp-up and flat-top stages have been carried out
  • Optimization of ramp-up process helped to save Volt-seconds consumptions from PF system
  • Simulations of Ohmic and ICRF heating scenario show a possibility to achieve stable plasma parameters
future work
Future work
  • Additional work on development of integrated plasma shape and position controllers is required
  • Integration of 2D-breakdown and DINA codes to do “all” scenario simulation ( breakdown-shutdown) in one step is desirable
  • A more accurate wave Altoke-e code, consistent with DINA, is planned to use for modeling ICRF heating