Transcript ht-7u asipp

ASIPP
Magnetic Diagnostics
of HT-7U Tokamak
Shen Biao Wan Baonian
Institute of Plasma Physics, CAS
P.O.Box 1126, Hefei, Anhui 230031, P.R.China
(e_mail: [email protected])
HT-7U
ASIPP
HT-7U
Outline
• Brief introduce of ht-7u.
• Principle and purposes of magnetic diagnostics.
• HT-7U magnetic diagnostic system.
• Summary.
ASIPP
HT-7U Tokamak
HT-7U
Main Parameters
Toroidal Field, Bo
3.5 T
Plasma Current, IP 1 MA
Major Radius, Ro 1.7 m
Minor Radius, a
0.4 m
Aspect Ratio, R/a
4.25
Elongation, Kx
1.6 - 2
Triangularity, d x 0.6 - 0.8
Heating andCurrent Driving:
ICRH
3 - 3.5 MW
LHCD
3.5 MW
ECRH
0.5 MW
Pulse length
1000 s
Configuration: double-null divertor,
single null divertor,
pump limiter
HT-7U
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Magnetic Diagnostics
Principle
• Electromagnetism
• Maxwell’s equations
  B  ( j 
D
)
t
B  0
 E  
D  
B
t
Purposes
•Equilibrium plasma configuration determination.
• for real time plasma control. (current, position,
shape, current profile, and disruption control) .
•MHD phenomena.
•Transient electromagnetic phenomena studies.
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Position/shape
Time resolution
Rate of change
Accuracy
Rin,Rout
1ms
100cm/s
0.5cm
Rx,Zx
1ms
100cm/s
0.5cm
Zc
1ms
100cm/s
0.5cm
Ip range
Time resolution
Rate of change
Accuracy
0.1-1MA
1ms
5MA/S
2%
Beta range
Time resolution
Rate of change
Accuracy
0.01<βp<5
1ms
1mWb/s
10-5
Parameter
Max.frequency
Spatial resolution
Accuracy
MHD
>100kHz
5cm
10%
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HT-7U
Sensor
Number
Position
Two-component
Magnetic probe
(42+27)*3
pol.*tor.
Inner vacuum vessel wall and behind the carbon shield
MHD probes
(Mirnov coils)
20*3
pol.*tor.
Inner vacuum vessel wall
Poloidal flux loops
31
Inner vacuum vessel wall
Saddle/locked loops
10*3
pol.*tor.
Inner vacuum vessel wall
In the low field area
Voltage loop
5
Inner vacuum vessel wall
Rogowski coil
1*3
por.*tor.
Inner vacuum vessel
Diamagnetic loop
1*3
por.*tor
Inner vacuum vessel and outer of vacuum vessel
8*4
behind the divotor
Vessel
monitor
structure
current
HT-7U
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HT-7U Magnetic Diagnostic System
1. Magnetic probes and Flux/voltage loops
Magnetic probes are
used to measure
poloidal magnetic field,
and flux loops are for
poloidal magnetic flux
measurement.
30 magnetic probes on vacuum vessel wall
17 behind carbon shield
39 flux loops on vacuum vessel wall
HT-7U
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Magnetic probes
four arrays in different positions
.
•for feedback control of plasma position and shape
•combine with other diagnostics is used for
reconstruction of plasma parameters
•study the MHD activities
•one array placed in toroidal direction equably
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HT-7U
• Isolation voltage >1000v
• Inductance:
2.20uh (tangential direction).
1.18uh (Normal direction)
• Resistance: 4.00 ohm
(tangential direction). 2.50ohm
• Analogue bandwidth: >10kHz
(Normal direction)
• Number of layers: 2
• Number of windings per coil: 160
• Effective winding area (A*N): tangential direction 1133cm2
Normal direction 1431cm2
ASIPP
Flux/voltage loops
cover all 16 segments in the
horizontal plane (toroidal
direction). 31 flux loops are
located inside the vacuum
vessel expect the horizontal
window and upper and down
windows near the divertor.
HT-7U
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HT-7U
2. Plasma Current Rogowasky Coil
• Rogowski coil is a
solenoidal coil whose
ends
are
brought
around together to form
a torus.
• It is used to measure plasma current
• One set include 2 Rogowski coils
One will be set around plasma inside vacuum wall.
Another one will be set outside the vacuum wall.
• Three sets will be set in different toroidal directions.
ASIPP
3. Saddle/locked-mode coils
One set of saddle/locked-mode coil
on the inside vacuum vessel wall
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HT-7U
• These coils are
used to measure poloidal
magnetic flux and detect the non-rotating or
slowly rotating of magnetic perturbations.
• The locked-mode coil will be placed on the outer
mid-plane inside the vacuum vessel .
• 5 saddle coils will be placed in the upper and 5 in
down positions near the divotors.
• Six to eight arrays will be installed in different
toroidal directions symmetrically.
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HT-7U
4. Diamagnetic Loops
• Diamagnetic loops
system includes
measurement loops,
compensation coils
and associated
processing electronics.
• It is used to measure plasma βp and plasma energy.
• Three sets are going to be mounted on the inner of
the vacuum vessel wall.
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HT-7U
Requirement
• The very small signal need to improve the signal to
noise ratio.
• Position must be vertical direction of the toroidal
field strictly to decrease the influence of toroidal field.
• The diamagnetic loop and compensation coil must
be parallel. Both of them set on the same framework.
• The position of system need to be adjusted to minimize
the influence of the poloidal field.
• Use ceramic or BN as framework.
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HT-7U
5. Measurement of Halo current
A poloidal halo current due to VDE is observed in most
large tokamak experiment. During plasma disruptions, a
current flow directly into a vacuum vessel from plasma. It
will produce an intense electromagnetic force on the invessel components.
• four sets of Rogowski coils are
installed behind the divertor tiles in
each toroidal location.
• The coils are installed to round
the roots of the divertor tiles.
• Four groups of these coils will be
set in different toroidal positions
HT-7U
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Special material
1. Cables (fiberglass)
• good vacuum
70 (1000)
0.000006
0.000005
Leakage ratio< 10e-6
• insulation
(Isolation voltage
>1000v)
• heat-resistant
>=300
Y Axis Title
0.000004
0.000003
0.000002
0.000001
0.000000
0
20
40
60
X axis title
80
100
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2. framework
• ceramic different to machine
• NB brittleness
3. vacuum feed-through
•32 molybdenum conductor
pins which gold plated
• Each pin is fasted and
insulated with glass sinter.
•The leak ratio is litter than
10-5Pal/s
HT-7U
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HT-7U
Protection and Improve the signal to noise ratio
Protection
• put behind graphite tiles
• put in a box or behind a sheet
Improve the signal to noise ratio
• output cable need to be twisted each other.
• stainless steel boxes or tapes could be
used as electric-magnetic shield.
• to avoid ground loops .
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Digital Integrator
Digital Signal
Processor
Integrator
D0~D31
Gain ratio
DSP
FPGA
V/F Converter
Controler
PGA
analog
signals
digital
signals
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HT-7U
Summary
• The progresses of HT-7U project in building,
and it is possible to get the first plasma
around 2005.
• Physical design of magnetic diagnostic for
HT-7U has been completed.
• Final engineering design for magnetic
diagnostics are under preparation.
HT-7U
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End and thanks