Tungsten-copper Divertor Development For EAST

ASIPPEAST

Tungsten-copper Divertor

Development For EASTPresent by D. -M. Yao

EAST-Divertor Group, ASIPP-Hefei, China

25th Symposium on Fusion Engineering

June 10-14, 2013, San Francisco, US

HT-7/EAST

ASIPP

Outline

1. Plasma-facing components for EAST

2. Necessity of W/Cu Divertor for EAST

3. Structural design, R&D for the W/Cu divertor

4. ITER-like mono-block W/Cu-PFCs development

5. Flat-type W/Cu-PFCs development

6. Summary

2013-6-11 225th SOFE, San Francisco US, June 10-14, 2013

HT-7/EAST

ASIPP

PFC for EAST


The EAST tokamak 6 campaigns operation ， PFCs have been upgraded in deferent stage. The 1st generati on di vertor (2006~2007)

Mo movable poloidal limiter + Stainless Steel PFCs for First Plasma and first campaign operation

HT-7/EAST

ASIPP

PFC for EAST


Active water-cooled PFC Tolerable heat flux <2MW/m2

Full C PFCFull C PFC

2008-20112008-2011

Mo First Wall + C DivrertorMo First Wall + C Divrertor

20122012

HT-7/EAST

ASIPP

Necessity of W/Cu Divertor


In the past years, the plasma heating power for EAST does not exceed 10 MW. Simulation results of divertor heat flux summarized as Below:

Divertor Pin (MW) ne, sep (1019/m3) Te,div (eV) qdiv (MW/m2)

CDN1.5 0.31 85 1.02.5 0.55 40 1.15.0 0.98 22 2.010.0 1.65 20 3.6

SN1.5 0.37 100 2.02.5 0.67 40 1.85.0 1.16 26 3.010.0 1.88 27 7.0

HT-7/EAST

ASIPP

Necessity of W/Cu Divertor


L-Mode

H-Mode

The heating power will be rapid increased to 20MW

HT-7/EAST

ASIPP

W/Cu Divertor Project Divertor

ITER-like configuration and structure, i.e., Monoblock targets (~10MW/m2) and W Flat-type dome and baffler (3~5MW/m2)

First wall Mo +CVD-W or W flat typeMax. heat flux capability 1~3MW/m2

Schedule2013-2014WUdiv + CLdiv + Mo (+ a new upper cryopump) 2015-2016Wdiv + MoFW +WFW(depends)


Target: W monoblock

FW: Mo tiles

2013 upper-div: W monoblock and flat-type

2013 low-div: Carbon tiles

HT-7/EAST

ASIPP

Structure design – supports

2013-6-11 25th SOFE, San Francisco US, June 10-14, 2013 8

Outer support

Inner support

Middle support

原热沉位置

现热沉位置

Poster: TPO-110Zibo Zhou

HT-7/EAST

ASIPP

Structure design – PFUs/CB


Flat type Wof ~2mm thick

Compact end-boxesfor cooling connects

End-boxesEnd-boxes

End-box design

Coolant fromCassette body

Monoblockunits ×4-5

Monoblock-W/Cu targets

• ~15,000 monoblocks• 720 monoblock-units• 240 flat-type mockups• E-beam employed for CuCrZr welding

HT-7/EAST

ASIPP

Structure design – CB assembly


Portnumber

Cassettenumber

Cassettes/port

PFUs/cassette

EAST 16 80 5 4/1/5ITER 18 54 3 16/34/22

•Tolerance of plasma- facing surface: toroidal: 2mm; neighbor: 0.5mm

HT-7/EAST

ASIPP

Structure design – cooling


Requirements for cooling• Surface temperature of W monoblock < 1200 ℃

• Maximum temperature of CuCrZr < 500 ℃• Water coolant, inlet temperature 20 , and ℃

temperature rise < 70 , to avoid boiling℃ (total length a set of PFU: 1329mm)

HT-7/EAST

ASIPP

R & D for structure/assembly


VV simulator for assembly of supports + CBs

HT-7/EAST

ASIPP

ITER-like W/Cu monoblocks

• ITER grade W has been manufactured in batch scale in Chinese Company

• W/Cu monoblocks: W&Cu bonded employing HIP technology


HT-7/EAST

ASIPP

ITER-like Monoblock W/Cu PFMC

2013-6-11 14

W/Cu mockup with W tiles was manufactured successfully by Hot Radial Pressing (HRP), showing good bonding between monoblocks and CuCrZr tube.

25th SOFE, San Francisco US, June 10-14, 2013

The testing W/Cu mockup with W monoblock tiles was manufactured by Hot Isostatic Pressing (HIP). And also successed.

HIP

Innovative technology combinations

HIP + HIP HIP + HRP

HT-7/EAST

ASIPP

HIP+HIP/HRP

HIP+HRP w/ 34 W-monoblocks ITER qualification mockup


===================================================

HIP+HIPEAST design

HT-7/EAST

ASIPP

Flat-type W/Cu PFMC

Flat-type W/Cu mockups have been being manufactured by means of various technologies

HIP & VHP: Step1:The interface of W/Cu were joined by HIP or vacuum hot pressing (VHP) at higher temperature of ~900 ℃, Step2: the interface of Cu/CuCrZr was bonded by VHP or HIP at temperature of 500~600℃.VPS & CVD coatings: Step1: Cu/CuCrZr by VHP / HIP, Step2: coating W on Cu.


HIP / VHPVPS / CVD

VHP

or gradient W/Cu layer

HT-7/EAST

ASIPP

VPS/CVD-W & Castellation


W

Cu

VPS-W

VPS-W W

Cu

W/Cu interlayers

CVD-W: WF6+3H2→W+6HF0.3~0.5mm/h, porosity <1%, 99.999wt.%

VPS-W: porosity 5-10%, 99.9wt%

HT-7/EAST

ASIPP

High Heat Flux Testing

23/4/21 18

A 60kW e-beam facility at SWIP

Mockup by HIP + HRP


HT-7/EAST

ASIPP

Thermal fatigue testing

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

HT-7/EAST

ASIPP

Ultrasonic NDT for monoblock-PFCs

Single reflector sensor, spiral scanning ultrasonic inspection of W/Cu interface

Cu

W

Defects > 2mm

Developed phased array, rotating reflector ultrasonic NDT inspection technologies.


HT-7/EAST

ASIPP

Prototype

Prototype of EAST divertor W/Cu armour was developed


HT-7/EAST

ASIPP

Summary

• The EAST Plasma H&CD power will be increased to 20MW in near future years, EAST upper divertor is being upgrade to ITER-like.

• Structure design,and R & D has been finished

batch manufacture has been satrted.

• First Cassette body and first plasma facing units have been made.

• The ITER-like W divertor expect operate before end of 2013


HT-7/EAST

ASIPP

2013-6-11 23

Thanks for your attention!

25th SOFE, San Francisco US, June 10-14, 2013

Documents

Tungsten-copper Divertor Development For EAST