ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.
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Transcript of ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.
![Page 1: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/1.jpg)
ASIPPEAST
Overview Of The EAST In
Vessel Components Upgraded
Presented by Damao Yao
![Page 2: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/2.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 2
1. First Plasma
2. First water cooled PFC
3. Upgrade
4. Summary
Outline
![Page 3: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/3.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 3
First Plasma
The first plasma of EAST was obtained in 2006 with all plasma facing material is stainless steel 316L, except graphite poloidal limiter.
![Page 4: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/4.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 4
First Plasma
![Page 5: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/5.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 5
First Water cooled PFC
![Page 6: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/6.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 6
First Water cooled PFC
![Page 7: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/7.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 7
First Water cooled PFC
![Page 8: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/8.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 8
First Water cooled PFC
Passive Stabilizer
Active fast feedback VS coils
![Page 9: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/9.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 9
Molybdenum First Wall
Mo FW + C DivrertorMo FW + C Divrertor
![Page 10: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/10.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 10
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 developed to enhance upper divertor
particle exhaust
Upgrade Background
![Page 11: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/11.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 11
Upgrade Background
EAST #41019@3034ms
Visible camera shows bright ELM
structure
Z (m
)
2 2.25
0
-0.5
Major radius R (m)
![Page 12: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/12.jpg)
HT-7/EAST
ASIPP
Upgrade Background
2014-10-08 12Presentation in fusion reactor division
L-Mode
H-Mode
Power Density to Divertor
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HT-7/EAST
ASIPP
Design Objective Accommodate plasma configuration
Module easy install and remove
Strong enough for plasma event
Heat load handling achieve 10MW/m2
Enough conductance for pumping
Apertures for diagnostics
W/Cu Divertor Design
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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 14
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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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 15
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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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 16
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)
![Page 17: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/17.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 17
Cooling water parameters optimization:
W/Cu Divertor Design
Inlet temperature Inlet velocity Outlet pressure
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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 18
Cassette Design
W/Cu Divertor Design
Supports
Pumping duct
Cooling water circuit
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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 19
Cassette Structure analysis:
Input data: Halo current Ih=25%Ip and TPF=2, Eddy current calculated by COMSOL code.
W/Cu Divertor Design
![Page 20: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/20.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 20
Divertor Development
Monoblock Development---HIP
Plasma facing surface perpendicularTo W material rolling direction
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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 21
W/Cu divertor R&D
W/Cu Divertor Development
Monoblock targetPrototype of Divertor module
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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 22
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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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 23
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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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 24
Divertor Development
Flat Type Development
HIP / VHPVPS / CVD
VHP
or gradient W/Cu layer
HIP
![Page 25: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/25.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 25
Divertor Development
HIP Flat Type Testing 5MW/m2; 15s on & 15s off
•NDT result after 1001 cycles
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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 26
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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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 27
VS coils Development
VS coils conductor:ITER like conductor technology : Pure copper conductor with water cooling, MgO powder insulation, SS jacket
SS316L JacketMgO Powder
Pure Copper
![Page 28: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/28.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 28
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.
![Page 29: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/29.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 29
RMP coils Design
3D view of the coil system with plasma configuration.
2D view of the coil system in poloidal cross section
![Page 30: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/30.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 30
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.
![Page 31: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/31.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 31
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
![Page 32: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/32.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 32
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.
![Page 33: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/33.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 33
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.
![Page 34: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/34.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 34
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
![Page 35: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/35.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 35
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
![Page 36: ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.](https://reader036.fdocuments.in/reader036/viewer/2022062801/56649e4d5503460f94b434b9/html5/thumbnails/36.jpg)
HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 36
Summary
RMP coils
Upper DivertorUpper Cryo-pump
VS coils
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HT-7/EAST
ASIPP
2014-10-08 Presentation in fusion reactor division 37
Summary
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HT-7/EAST
ASIPP
Summary
2014-10-08 Presentation in fusion reactor division 38
The EAST plasma heating power will be significant update
To meet advance plasma high performance the EAST in-vessel components should be updated
W/Cu divertor will be handle 10MW/m2 for steady state and 15MW/m2 for transient
RMP coils are developed for multiple functions, VS coils are relocated for more efficient vertical instability control
Updated EAST in-vessel components are in operation and will demonstrate their reliability
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HT-7/EAST
ASIPP
2014-10-08 39
Thanks for your attention!
Presentation in fusion reactor division