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

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2013-11-07 APFA 2013 Korea 2

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



4. RMP coils design

5. Second Cryopump

6. Summary

Outline

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2013-11-07 APFA 2013 Korea 4

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

2013-11-07 6APFA 2013 Korea

L-Mode

H-Mode

Power Density to Divertor

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1. Background



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.


Flat W/Cu with cooling channel

W Monoblockstructure

End box

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Monoblock design and optimization:


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（

）


3 4 5 6 7

400

500

600

700

800

900

1000

K温

度（

）


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（

）


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（

）


22 24 26 28 30 32 34 36 38 40 42300

400

500

600

700

800

900

K温

度（

）


H(mm)

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Cooling water parameters optimization:


Inlet temperature Inlet velocity Outlet pressure

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Cassette 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.


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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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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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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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Flat Type Development

HIP / VHPVPS / CVD

VHP

or gradient W/Cu layer

HIP

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HIP Flat Type Testing 5MW/m2; 15s on & 15s off

•NDT result after 1001 cycles

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1. Background



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



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



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



4. RMP coils design

5. Second Cryopump

6. Summary

Outline

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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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Summary

2013-11-07 APFA 2013 Korea 35

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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2013-11-07 36

Thanks for your attention!

APFA 2013 Korea

design of east upgraded in vessel components

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