Design Of EAST Upgraded In Vessel Components
description
Transcript of Design Of EAST Upgraded In Vessel Components
ASIPPEAST
Design Of EAST Upgraded In
Vessel ComponentsPresented by Damao Yao
9th APFA
November 05-08, 2013, Gyeongju, Korea
HT-7/EAST
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1. Background
2. W/Cu Divertor Design
3. VS coils design and relocation
4. RMP coils design
5. Second Cryopump
6. Summary
Outline
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1. Background
2. W/Cu Divertor Design
3. VS coils design and relocation
4. RMP coils design
5. Second Cryopump
6. Summary
Outline
HT-7/EAST
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The EAST plasma heating power is updating to 20MW with LHCD 10MW, ICRH 8MW and NBI 2MW, and for further updating: ICRH up to 12 MW, NBI up to 8MW and ECRH up to 6MW. Divertor heat flux will up to 10MW/m2
ELMs was observed in EAST last operation campaign To obtain high plasma performance error field
correction is necessary in EAST VS coils are relocated to get more efficient vertical
stability control Upper cryopump join to enhance upper divertor
particle exhaust
Background
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Background
EAST #41019@3034ms
Visible camera shows bright ELM
structure
Z (m
)
2 2.25
0
-0.5
Major radius R (m)
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Background
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L-Mode
H-Mode
Power Density to Divertor
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1. Background
2. W/Cu Divertor Design
3. VS coils design and relocation
4. RMP coils design
5. Second Cryopump
6. Summary
Outline
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Structure design: EAST W/Cu divertor focus on ITER like structure and technology.
W/Cu Divertor Design
Flat type Wof ~2mm thick
End-boxesEnd-boxes
Monoblock-W/Cu targets
Compact end-boxesfor cooling connects
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W target design: Tungsten plasma facing target design as monoblock structure for vertical target and flat structure for baffle.
W/Cu Divertor Design
Flat W/Cu with cooling channel
W Monoblockstructure
End box
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Monoblock design and optimization:
W/Cu Divertor Design
6 7 8 9 10
400
500
600
700
800
900
1000
(mm)
K温
度(
)
TW max, TW av, TCU max, TCU av, TCUCRZR max, TCUCRZR av,
20 30 40 50 60 70 80
400
800
1200
1600
2000
2400
L(mm)
K温
度(
)
TW max, TW av, TCU max, TCU av, TCUCRZR max, TCUCRZR av,
3 4 5 6 7
400
500
600
700
800
900
1000
K温
度(
)
TW max, TW av, TCU max, TCU av, TCUCRZR max, TCUCRZR av,
r1(mm)
0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 2.0 2.2300
400
500
600
700
800
900
K温
度(
)
TW max, TW av, TCU max, TCU av, TCUCRZR max, TCUCRZR av,
mm
0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 2.0 2.2300
400
500
600
700
800
900
mm
K温
度(
)
TW max, TW av, TCU max, TCU av, TCUCRZR max, TCUCRZR av,
22 24 26 28 30 32 34 36 38 40 42300
400
500
600
700
800
900
K温
度(
)
TW max, TW av, TCU max, TCU av, TCUCRZR max, TCUCRZR av,
H(mm)
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Cooling water parameters optimization:
W/Cu Divertor Design
Inlet temperature Inlet velocity Outlet pressure
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Cassette Design
W/Cu Divertor Design
Supports
Pumping duct
Cooling water circuit
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Cassette Structure analysis:
Input data: Halo current Ih=25%Ip and TPF=2, Eddy current calculated by COMSOL code.
W/Cu Divertor Design
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Divertor Development
Monoblock Development---HIP
Plasma facing surface perpendicularTo W material rolling direction
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W/Cu divertor R&D
W/Cu Divertor Development
Monoblock targetPrototype of Divertor module
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Divertor Development
Defects > 2mm
Spiral scanning ultrasonic NDT of W/Cu interface
Probe of phased array ultrasonic
• Phased Array ultrasonic has abilities uniquely :- High-speed tube inspection through electronic
scanning- Inspection of components made of multiple
dissimilar materials
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Divertor Development
Heat load ~ 8.4MW/m2, cooling water of 2m/s, 20℃, 15s/15s on/off cycles.
The mock up survived up to 1000 cycles, with surface temperature up to 1150℃.
The temperature difference of cooling water between inlet and outlet raised up to 18℃.
Cycle 1
Cycle 1000
Cycles 1-2
Cycles 999-1000
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Divertor Development
Flat Type Development
HIP / VHPVPS / CVD
VHP
or gradient W/Cu layer
HIP
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Divertor Development
HIP Flat Type Testing 5MW/m2; 15s on & 15s off
•NDT result after 1001 cycles
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1. Background
2. W/Cu Divertor Design
3. VS coils design and relocation
4. RMP coils design
5. Second Cryopump
6. Summary
Outline
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VS coils relocation
Position 1
Current Position
Old position
Position 3
Gfile VDE growth rate(/s)
Old position
Position 1 Current Position
Position 3
120317
.01010 212 78 78 360
.01020 298 95 107 504
.01030 403 110 141 682
.01040 516 117 177 867
120318
.01010 291 107 111 485
.01020 431 134 155 732
.01030 546 144 189 935
.01040 740 157 244 1284
120319
.01010 450 158 169 755
.01020 629 181 219 1095
.01030 959 214 294 1799
.01040 3959 345 596 24706
120320
.01010 591 200 220 1002
.01020 1084 263 331 2092
.01030 1704 300 434 3822
.01040 N.A 3347 N.A N.A
120321
.01010 161 59 56 286
.01020 215 70 75 372
.01030 253 71 87 432
.01040 2053 273 388 6686
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VS coils Development
VS coils conductor:ITER like conductor technology : Pure copper conductor with water cooling, marmag powder insulation, SS jacket
SS316L JacketMgO Powder
Pure Copper
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VS coils installed in VV
Two turns VS coils up-down symmetry, each turn with two feeders through VV port, and connected outside VV. The coils are winding inside VV.
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1. Background
2. W/Cu Divertor Design
3. VS coils design and relocation
4. RMP coils design
5. Second Cryopump
6. Summary
Outline
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RMP coils Design
3D view of the coil system with plasma configuration.
2D view of the coil system in poloidal cross section
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RMP coils Design
Functions and parameters of RMP Coils
FunctionPulse
st(s)/
Pulset_total(
s)Current
Frequence(Hz)
Error field correction
25000
40100000
01kAt 0
ELM control 5000 10 50000 10kAt0(80%) ,50(
20%)
RWM Control 2500 5 12500 1kAt <= 1000
The design parameter assume that EAST have 5,000 shots per year and the coil will be used for 10 years with 50,000 shots.
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RMP coils Development
Conductor design
ITER Like conductor structure
- Copper conductor with active cooling
water
- 3mm thickness MgO powder
insulation layer
- 2mm thickness SS-316L Jacket Max. Current of conductor : 3kA
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RMP coils Development
8 RMP Coils upper and down , curvature in toroidal direction and straight in poloidal direction. 4 turns for each coil. Coils support to VV, and protected by Copper plate with Mo tiles attached.
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1. Background
2. W/Cu Divertor Design
3. VS coils design and relocation
4. RMP coils design
5. Second Cryopump
6. Summary
Outline
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Second Cryo-pump
Cryo-pump DesignThe upper Cryo-pump Structure is same as lower cryo-pump (DIII-D like type). i.e. tube inside tube structure with liquid helium stabilizer at center then He tube, then 80 K thermal shield, then VV temperature thermal shield.
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Second Cryo-pump
Cryo-pump manufacturing Installation
The cryo-pump design nominal pumping speed is127m3/s, and effective pumping speed is 37m3/s (for N2), effective pumping speed for D2 is ~80m3/s, for H2 is ~110m3/s
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1. Background
2. W/Cu Divertor Design
3. VS coils design and relocation
4. RMP coils design
5. Second Cryopump
6. Summary
Outline
HT-7/EAST
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Summary
Full C PFCFull C PFC Mo FW + C DivrertorMo FW + C Divrertor
20102010 20122012
First PlasmaFirst Plasma
20142014
Mo FW+W&C DivertorMo FW+W&C Divertor
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Summary
RMP coils
Upper DivertorUpper Cryo-pump
VS coils
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The EAST plasma heating power will have significant increased
To meet high plasma performance EAST in-vessel components should be updated
W/Cu divertor will be ITER like technology first time applied in real tokamak
VS and RMP coils are ITER like in vessel coil technology, it can demonstrate ITER IVC technology
Updated EAST is expected start operation around February 2014
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Thanks for your attention!
APFA 2013 Korea