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托卡马克的平衡计算 - PowerPoint PPT Presentation

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托卡马克的平衡计算. 李国强 2013.12.18 四室学术报告. Introduction. Decompose the physics problem by the orders (time order and space order) Traditional decomposition of plasma physics (by time order): equilibrium, stability and transport Equilibrium is the basis for other problem

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2013.12.18 四室学术报告

  • Decompose the physics problem by the orders (time order and space order)
  • Traditional decomposition of plasma physics (by time order): equilibrium, stability and transport
  • Equilibrium is the basis for other problem
  • Here the equilibrium means the state of force equilibrium
introduction cont
Introduction (cont.)
  • Force balance equation (static momentum equation)
  • Force balance equation in 2D form → Grad-Shafranov (G-S) equation (For axis symmetric, in (R,z) coordinate):
  • Then the solution of the G-S equation describes the properties of the equilibrium
equilibrium and p oloidal field coils
Equilibrium and poloidal field coils
  • Poloidal field coils induct the ohmic plasma current and control the plasma shape
  • On EAST
    • PF1-PF6, center solenoid, mainly for the ohmic current
    • PF7/9, elongation
    • PF11,PF13, trianglarity
    • PF5, PF7/9, PF11, divertor control

EAST PF coils and plasma


properties of equilibrium
Properties of equilibrium
  • Plasma configuration
    • Embedded flux surface
    • Plasma geometry
    • Divertor configuration
  • Profiles (functions of flux surface)
    • : pressure
    • : no direct physical meaning, but direct in G-S equation
    • : safety factor, describe the pitch angle of magnetic field line
    • : flux surface averaged parallel current
    • , q and are not independent
fixed boundary and free boundary equilibrium calculation
Fixed boundary and free boundary equilibrium calculation
  • Fixed boundary
    • The plasma boundary is given, only calculate the plasma configuration inside the plasma
    • Easy to calculate, useful for theory study
  • Free boundary
    • To calculate the configuration outside the plasma boundary
    • The current in the PF coils is given
    • Complicate but sometimes necessary
  • A third kind
    • Prescribe a non-fixed plasma boundary
coordinate system
Coordinate system
  • Many kinds of coordinate system in tokamak study
  • Two major coordinate systems: (R,z) coordinate and magnetic surface coordinate
  • coordinate system
    • For free boundary calculation
    • Can handle the X-point



Mesh in (R,z) coordinate

coordinate system cont
Coordinate system (cont.)
  • Flux surface coordinate system
    • coordinate
    • Easier, but cannot handle the X-point
    • can be
      • Orthogonal
      • Equal arc length
      • ……
  • Some coordinate equivalence
    • normalized toroidal flux
    • normalized volume

Mesh in flux surface coordinate

equilibrium construction and reconstruction
Equilibrium construction and reconstruction
  • Construction
    • Generate an equilibrium from given profiles, plasma shape or current in PF coils, and other parameters
    • Basis for tokamak design
    • Basis for many theory study
  • Reconstruction
    • Find the experimental equilibrium from the diagnostic data
    • Basis for experiments analysis
equilibrium reconstruction with efit
Equilibrium reconstruction with EFIT
  • EFIT is the most popular code for equilibrium reconstruction. Maybe the most popular code in tokamak research area
  • Assume a polynomial or spline profiles of P’ and FF’, then iteratively find the coefficient to minimize the error quality function
different efit reconstruction constraints
Different EFIT reconstruction constraints
  • At present, EAST only has the magnetic diagnostics and limited kinetic diagnostics
  • But we can add some constraints to the current profile
magnetic diagnostic constraints
Magnetic diagnostic constraints
  • All kinks of magnetic probe and flux loops

Strait (2007)

kinetic profiles on east
kinetic profiles on EAST
  • Te and ne are from Thomson scattering
  • Ti is from the XCS, but only central region data are available. So Ti is scale from Te and assume Ti=Te at the edge region
  • First map the data to space, then fit them with tension spline
  • Assume flat Zeff=2.5
  • At present EAST has no NBI, so the fast ion contribution is neglected

Data and fitting profiles for 38300.3900

edge current constraint for h mode plasma
Edge current constraint for H-mode plasma
  • For H-mode plasma, it is believed that at the edge region, the current is dominated by the bootstrap current
  • Sauter bootstrap current model is used to calculate the bootstrap current. Bootstrap current calculation relies on the kinetic profiles (Te, Ti, ne, Zeff)
  • Ohmic current

EAST 38300, 3900ms

Typical pressure and current profiles

of H-mode plasma at edge region

Bootstrap current at the edge region

kinetic equilibrium reconstruction on east
Kinetic equilibrium reconstruction on EAST
  • With the constrains of magnetic diagnostics, pressure profile, edge current profile, we achieved the kinetic equilibrium
  • The current/q profiles at the central region are not reliable, though we have the global li constrain

38300, 3900ms

Pressure, current profiles and configuration from kinetic EFIT and magnetic EFIT

equilibrium construction
Equilibrium construction
  • Lots of codes for equilibrium construction, most of them are fixed boundary codes
    • CORSICA has both direct and inverse solver
      • Inverse solver: coordinate, solve for R, Z, fixed boundary
      • Direct solver: coordinate, solve for , free boundary
    • CORSICA can easily change the plasma shape and profiles
construct self consistent equilibrium
Construct self-consistent equilibrium
  • To construct a self-consistent equilibrium, the self-consistent plasma shape and profiles must be given
  • Self-consistent profiles:
    • Bootstrap current dominated edge current
    • Self-consistent pedestal height and width, EPED model
    • EPED model (peeling-ballooning model + kinetic ballooning model, ELITE+BALOO) has successfully predict the pedestal height and width
  • This technic could be useful for EAST and CFETR