Operational scenario of ktm dokuka v n khayrutdinov r r triniti russia
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OPERATIONAL SCENARIO of KTM Dokuka V.N., Khayrutdinov R.R. TRINITI, Russia - PowerPoint PPT Presentation


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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


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


Scheme of discharge scenario at KTM processes 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) processes at KTM

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


Ramp up 1
Ramp-up (1) processes at KTM

  • 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 processes at KTM

  • 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 processes at KTM

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) processes at KTM

  • 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 processes at KTM

time= 9 ms

time= 279 ms

time= 499 ms

time= 3999 ms



Ramp up initial equilibrium
Ramp –up (initial equilibrium) processes at KTM

Plasma equilibrium during ramp-up


Equilibrium at the end of ramp-up processes at KTM

Plasma equilibrium during ramp-up


Ramp up profiles
Ramp –up (profiles) processes at KTM

  • Plasma current density profiles

  • Safety factor profiles

  • Electron temperature profiles

  • Bootstrap current profiles



Flat top
Flat-top processes at KTM

  • 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



Pf currents scenario pf1 pf6 cs hfc
PF currents scenario processes at KTM(PF1-PF6, CS, HFC)


Flat top typical configuration
Flat-top (typical configuration) processes at KTM

Plasma equilibrium during flat-top


Evolution of plasma parameters 1
Evolution of plasma parameters processes at KTM 1

  • Plasma current

  • Poloidal beta

  • Minor radius

  • Horizontal magnetic axis


Evolution of plasma parameters 2
Evolution of plasma parameters processes at KTM 2

  • Averaged electron density

  • Elongation

  • Internal inductance

  • Vacuum vessel current


Evolution of plasma parameters 3
Evolution of plasma parameters processes at KTM 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 processes at KTM 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 processes at KTM 5

  • Vertical position of magnetic axis

  • Bootstrap current

  • beta

  • Normalized beta


Evolution of plasma parameters 6
Evolution of plasma parameters processes at KTM 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 processes at KTM 7

  • Total Volt-seconds

  • Plasma Volt-seconds

  • External Volt-seconds

  • Ion confinement time


Evolution of plasma parameters 8
Evolution of plasma parameters processes at KTM 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 processes at KTM 9

  • Minor radius (95%)

  • Upper elongation (95%)

  • Down elongation (95%)

  • Elongation (95%)


Evolution of plasma parameters 10
Evolution of plasma parameters processes at KTM 10

  • Upper triangularity (95%)

  • Down triangularity (95%)

  • Triangularity (95%)

  • Horizontal position of magnetic axis


Evolution of plasma parameters 11
Evolution of plasma parameters processes at KTM 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) processes at KTM

  • Plasma current density profiles

  • Safety factor profiles

  • Electron temperature profiles

  • Bootstrap current profiles


Flat top profiles 2
Flat-top (profiles –2 ) processes at KTM

  • Plasma current density profiles

  • Safety factor profiles

  • Electron temperature profiles

  • Bootstrap current profiles


Flat top profiles 3
Flat-top (profiles –3) processes at KTM

  • Plasma current density profiles

  • Safety factor profiles

  • Electron temperature profiles

  • Bootstrap current profiles


Volt seconds balance
Volt-seconds balance processes at KTM


Conclusions
Conclusions processes at KTM

  • 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 processes at KTM

  • 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




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