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M J Schaffer, T'E' Evans,

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TRIP3D magnetic line tracing code to identify stochasticity (by T.E. Evans) ... on low-field side advance poloidally almost all at the same rate (blue dots) ... – PowerPoint PPT presentation

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Title: M J Schaffer, T'E' Evans,


1
PRELIMINARY STUDY OFITER CORRECTION COILSFOR
ELM SUPPRESSION
  • by
  • M J Schaffer, T.E. Evans,
  • General Atomics
  • R A Moyer1, P R Thomas2, M Bécoulet2,
  • Y Gribov3, V A Chuyanov3
  • 1UCSD
  • 2CEA Cadarache
  • 3ITER
  • Presented at the 45th APS-DPP Annual Meeting
  • Jülich, Germany
  • 2005 March 1517

2
Why Suppress ELMs?
  • ELMs are driven by a combination of large
    pressure gradient and current density at the edge
    of H-mode plasmas.
  • ELMs are beneficial
  • For a slight confinement penalty, ELMs halt the
    unchecked density increase (hydrogenic and
    impurity) that leads to radiative termination of
    pure H-mode.
  • ELMs are damaging
  • In a large tokamak like ITER, Type-1 ELMs release
    so much plasma energy in such a short time, that
    they would ablate divertor target material.
    Calculated target lifetime is unacceptably short.
  • Suppression of Type-1 ELMs is considered a
    necessary ITER goal.
  • Suppression must function over the range of ITER
    plasma parameters without serious degradation of
    confinement.
  • ELM suppression has been achieved by weak
    externally-applied magnetic perturbations in some
    DIIID regimes and is being studied.

3
ITER-Shape Plasmas in DIIID are 1/3.6 ITER Size
ITER Correction Coil Set is Scaled by the Same
Ratio for Modeling
ITER Correction Coils (Scaled to DIII-D)
DIII-D with DIII-D Perturbation Coils (I- and
C-Coils)
C-Coil
I-Coil
I-Coil
ITER plasma shape with q surfaces
4
Numerical Tools
  • TRIP3D magnetic line tracing code to identify
    stochasticity (by T.E. Evans)
  • Fourier harmonic (m,n) analysis code SURFMN (by
    M.J. Schaffer)
  • Both codes...
  • Obtain axisymmetric equilibrium B from EFIT
  • Plasma-generated toroidal and poloidal B treated
    independently of all external fields and of each
    other
  • Model externally-generated vacuum field
    contributions realistically
  • PF- and TF-coils with measured errors
  • DIIID C-coil (set of 6 ex-vessel coils)
  • DIIID I-coil (set of 12 in-vessel coils)
  • ITER correction coils (scaled down 3.6 times to
    DIII-D size)
  • Point dipoles, miscellaneous loops, TF ripple,

5
Fourier Analysis on an Axisymmetric Toroidal
Magnetic Surface
  • Procedure
  • Set up straight-magnetic-line coordinate system
    on the surface q f/q
  • q, f are poloidal, toroidal angle variables
    interval 0,2p
  • Use the corresponding Jacobian when integrating
    over the surface
  • where
  • First parenthesis factor of J is constant on a
    magnetic surface, but R3 and Bq vary. They
    reduce contributions from small-R side and tips,
    respectively.
  • Then,
  • Tested Fourier analysis of on a surface
    against magnetic island properties
  • Fourier Bmn on resonant surface yields same
    island width as Poincaré plot
  • Equal and opposite Bmn from two different sources
    yield null m,n island in Poincaré plot

6
DIIID Experiments Are Studying ELM
Suppressionby Weak External Magnetic
Perturbations
  • C-coil field was not very effective in ELM
    suppression attempts
  • I-coil fields are more effective
  • 2003 At high triangularity, high ne
  • Weak resonant perturbation with odd I-coil
    parity was most effective.
  • Comparable with DIIID intrinsic error and seemed
    to interact with it.
  • Damped plasma rotation.
  • 2005 At lower triangularity, low ne
  • Stronger resonant perturbation with even I-coil
    parity worked well but began to show confinement
    degradation.
  • Lots of new data in last few days.
  • Rotation, braking, confinement still being
    analyzed.
  • What is important? Stochasticity? Braking? Mix
    with multiple n (errors or planned)?
  • What to specify for ITER ELM-control coils?
  • DIIID goal Establish a physics basis for
    design of ELM control coils on larger tokamaks
    such as JET and ITER.

7
C-Coil Makes a Simple m,n3 Spectrum
Normalized Poloidal Flux
-20 m0 20
  • Does not generate n3 field efficiently at pitch
    resonance.Large components at small m.

8
ODD-Parity I-Coil m,n3 Spectrum Has a Null
ValleyClose to the Pitch Resonant Surfaces a
Weak Perturbation
Valley
Asterisks indicatepitch resonanceq n/m
Ridge
  • This was the best ELM-suppressing spectrum in
    the first experiments.Has large components at
    intermediate m.

9
EVEN-Parity I-Coil m,n3 Spectrum Has a
RidgeClose to the Pitch Resonant Surfaces a
Stronger Perturbation
Ridge
  • This spectrum suppressed ELMs well in the low
    density experiments.It generates pitch-resonant
    components more efficiently.
  • Has suppressed ELMs well in 2005 experiments.

10
Ridge and Valley Parallel to Pitch Resonanceis
a Result of the Tokamak Geometry at the Usual
Aspect Ratio
ODD
EVEN
  • Outer magnetic lines on low-field side advance
    poloidally almost all at the same rate (blue
    dots).
  • They are perturbed similarly.
  • Magnetic shear and q are
  • determined at tips and small R.
  • DIIID outer magnetic lines traverse between
    bottom and top I-coil centers in about 120
    toroidal degrees (figures drawn close to scale).
  • DIIID C-coil centers are almost in line, so C-
    and I-coil contributions can be added or
    subtracted.
  • Choice of handedness in case of odd-parity I-coil

11
Example of a Left-Hand-Dominant m,3
SpectrumOdd-Parity I-Coil with C-Coil
-20 m0 20
  • Right-handed components attenuated But does not
    make pitch-resonant field efficiently

12
Adding C-Coil and I-Coil Fields in Phase Makes
the Strongest Resonant B in DIIID
  • Presumably this combination makes the greatest
    stochasticitybut it offers no control of
    handedness

13
ITER Midplane Error Correction CoilsMake an m,3
Spectrum Much Like the DIIID C-Coil
m,3 Spectrum at 95 flux, q95 3
-16 m0 16
-20 m0 20
  • Does not generate n3 field efficiently at
    pitch resonance.Large components at small m.
  • Adding top bottom coils makes only small
    differences.

14
Port Plug Dipoles (in all 18 ports) Make an m,3
SpectrumPeaked Near Pitch-Resonance
m,3 Spectrum at 95 flux, q95 3
-16 m0 16
-20 m0 20
  • This spectrum looks more useful.
  • (Model was a point-dipole array, not current
    loops. Might not be accurate.)

15
12 Internal Coils Above and Below Midplane (Like
DIIID)Can Make a m,3 Spectral Peak Matched to
Pitch Resonance
m,3 Spectrum at 95 flux, q95 3
-16 m0 16
-20 m0 20
  • Possibly a good m,3 spectrum, matched to pitch
    resonance.
  • Coil proportions to get this spectrum are almost
    same as DIII-D I-coil,
  • but these coils are farther from plasma
    separatrix than the DIII-D I-coils.

16
Some Discussion and Conclusions
  • It is not known yet (2005 mar 11) what
    perturbation spectral features are essential for
    Type-1 ELM suppression, and what features must be
    avoided.
  • DIIID is investigating this problem, within the
    possibilities of the DIIID coil set.
  • DIIID C-coil has not suppressed the ELMs
    effectively.
  • Physics is still unknown.
  • ITER error correction coil set spectra are not
    much different from C-coils.
  • ITER ELM suppression by magnetic perturbation
    would probably need dedicated coils.
  • DIIID I-coil does suppress ELMs effectively.
  • Internal coils are difficult in ITER.
  • We do not understand the physics of rotation
    damping.
  • Gaining ELM suppression while avoiding rotation
    damping and confinement degradation might require
    still more complicated coil arrays, e.g.,
  • Multiple toroidal harmonics
  • Arrays both far from and close to the midplane,
    to cancel undesired features
  • What will the plasma really do, and why?. . . .
    . Stay flexible.
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