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ELM Suppression by Edge Ergodisation

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relatively easy installation (flexible cable) 'Railway company cable' - 3kV ... Cables from north wing to machine. Route is well known. ... – PowerPoint PPT presentation

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Title: ELM Suppression by Edge Ergodisation


1
ELM Suppression by Edge Ergodisation
  • P. Thomas, M. Bécoulet , M.Lipa, E. Nardon, P.
    Ghendrih, A. Grosman G. Huysmans, - CEA Cadarache
  • R. Moyer, T.Evans General Atomic
  • K.H. Finken KFZ Juelich
  • V. Chuyanov, G.Federici, R. Tivey ITER Garching
  • S. Hotchin, L. Last UKAEA Culham
  • M.Dentan EFDA-CSU Culham
  • many others who are indirectly(as yet!)
    implicated.

2
Plan of Presentation
  • Scientific rationale
  • DIIID experiment with I-coils
  • Programmatic logic
  • ELM suppression for ITER
  • An ITER prototype RMP system for JET
  • The project programme

3
Scientific rationale
Large type I ELMs (Edge Localised Modes) in ITER
will
  • seriously reduce the lifetime of the divertor
    target either by causing intolerably high
    sputtering rate of a graphite target or surface
    melting of tungsten
  • cause considerable operational difficulty in
    advanced scenarios, through coupling between core
    and edge
  • interrupt the coupling of ICRH and LHCD and
  • reduce the effectiveness of the divertor.

4
How can edge ergodisation eliminate ELMs?
  • Magnetic perturbation, resonant with q at edge
  • ? ergodisation
  • ? increased edge transport.
  • ? decreased ?p
  • ? edge MHD stable
  • ? ELM suppression

5
How should we pursue the idea?
  • ELM control necessary for ITER
  • Edge ergodisation only method that suppresses
    ELMs and retains confinement quality
  • Understand and expand DIIID results
  • Prepare a feasible, conceptual design for ITER
  • Prepare a design for an ITER prototype to be
    installed on JET

6
The DIII-D I-coils (Internal MHD coil) provide a
resonant perturbation to test this idea
  • I-coils installed for MHD investigations.
  • n3 symmetry with spectrum m9-12
  • Inside vacuum chamber very close to plasma (
    a/6).

7
The I-coils, being close to the plasma, have a
strong resonant component at the edge.
zeros in ?Br
.but the interior perturbations are of the same
order.
8
The initial experiments suppressed type I ELMs
whilst maintaining bN.H 4.2
  • Edge ergodisation is only proposal for ELM
    suppression.

9
The toroidal rotation velocity is strongly
reduced during ELM suppression
  • Core v? drops by factor 3
  • No sign of increased susceptibility to NTMs.
  • Momentum input evidently enough.
  • What of ITER?

10
What do we need to understand at DIIID?
  • It is not completely evident why the ELM
    suppression is occurring...........
  • No obvious signs of edge profile erosion, execept
    with 60 phasing.
  • Our interpretation is that we just touch the
    threshold for ergodisation.
  • Therefore do experiments with much larger dB/BT
  • Direct coupling to edge modes?
  • Does the toroidal braking matter?
  • Can we be assured that v? will always be
    sufficient to prevent RMP induced NTMs(even in
    ITER)?
  • Relationship to type II ELMs?
  • Experiment at GA last week?

11
Opportunities for coil emplacment in ITER are
limited.
  • Can either use the PF coil positions like the
    error field correction system or the port plugs.
  • All possible positions are 1-2 minor radii from
    plasma.

12
The port-plug coils looked attractive..
16 turns
1.8 x1.4 m
G.Federicci R.Tivey V.Chuyanov
  • Coaxial actively cooled conductor winding
    embedded in port plug walls.

13
.but no easy way to cancel core perturbation.
large compensation coils
port-plug coils
  • The resonant components are nearly independent
    of coil size because of equilibrium geometry
    around separatrix.
  • Unwanted components not so very different to
    DIIID if it is remembered that island width
    dB0.5

14
..and edge spectrum intrinsically less good
  • The two spread-out zeros for simple dipolar coil
    systems reduce the high-m components
  • The expansion of ? near separatrix is only
    thing that rescues us

15
Where to install coils on JET?
Available 100-200kAt needed again 2a from
plasma
16
Can devise coil sets with flat resonant
perturbation profiles.
  • Solutions exist, like the above, with island
    widths in core lt2cm and reasonable Chirikov
    parameter at edge.
  • It looks as if we will have to live with core
    perturbations!

17
Engineering for Coils
  • 10-20s at max current, inertially cooled design,
    using cables.
  • gt of the order of 2Meuro
  • Same technology as the error field correction
    coils.
  • gt relatively easy installation (flexible
    cable)

Shims to set compression of cables
Railway company cable - 3kV
Insulating and restraining elastomer padding
10kV
Aluminium case or clamps
100kAt winding
18
Power Supplies
  • Use old PRFA 3kA/3kV/20s
  • Needs some repair work.
  • Cables from north wing to machine.
  • Route is well known.
  • Need new 33kV transformer this is also required
    for other reasons.

19
Planning for 2005 conceptual design activity
  • Outline planning, assuming end 2008 installation

20
Planning for 2005 conceptual design activity
21
Interfaces will require careful consideration
  • Neutral beam sensitivity to perturbation field
    will have to be assessed
  • gt re-ionised particles in duct!!
  • Interaction with diagnostics will be considered
  • gt in particular with magnetic probes
  • Position control will have to be modified.
  • Forces on coils will have to be calculated, both
    for normal and off-normal operation.
  • Electrical pick-up during VDEs will have to be
    estimated and insulation chosen appropriately.

22
The Future
  • Edge ergodisation holds considerable promise for
    ELM suppression in ITER.
  • It is the only proposed method for suppression
    and has been proven on DIIID.
  • It does not reduce energy confinement.
  • However, practical implementations for ITER and
    JET are proving to be less straightforward than
    had been hoped, with respect to currents required
    and core perturbations.
  • Nevertheless, a worthwhile proof-of-principle
    ITER Prototype can be mounted on JET in the
    2008/9 shutdown at a cost 2Meuro.
  • A detailed design will be ready by the end of
    2005.
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