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ASIPP EAST Tungsten-copper Divertor Development For EAST Present by D. -M. Yao EAST-Divertor Group, ASIPP-Hefei, China 25 th Symposium on Fusion Engineering.

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Presentation on theme: "ASIPP EAST Tungsten-copper Divertor Development For EAST Present by D. -M. Yao EAST-Divertor Group, ASIPP-Hefei, China 25 th Symposium on Fusion Engineering."— Presentation transcript:

1 ASIPP EAST Tungsten-copper Divertor Development For EAST Present by D. -M. Yao EAST-Divertor Group, ASIPP-Hefei, China 25 th Symposium on Fusion Engineering June 10-14, 2013, San Francisco, US

2 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 2013-6-11125th SOFE, San Francisco US, June 10-14, 2013

3 HT-7/ EAST ASIPP PFC for EAST 2013-6-11225th SOFE, San Francisco US, June 10-14, 2013 The EAST tokamak 6 campaigns operation ， PFCs have been upgraded in deferent stage. Mo movable poloidal limiter + Stainless Steel PFCs for First Plasma and first campaign operation

4 HT-7/ EAST ASIPP PFC for EAST 2013-6-11325th SOFE, San Francisco US, June 10-14, 2013 Active water-cooled PFC Tolerable heat flux <2MW/m 2 Full C PFC 2008-2011 Mo First Wall + C Divrertor 2012

5 HT-7/ EAST ASIPP Necessity of W/Cu Divertor 2013-6-11425th SOFE, San Francisco US, June 10-14, 2013 In the past years, the plasma heating power for EAST does not exceed 10 MW. Simulation results of divertor heat flux summarized as Below: DivertorP in (MW)n e, sep (10 19 /m 3 )T e,div (eV)q div (MW/m 2 ) CDN 1.50.31851.0 2.50.55401.1 5.00.98222.0 10.01.65203.6 SN 1.50.371002.0 2.50.67401.8 5.01.16263.0 10.01.88277.0

6 HT-7/ EAST ASIPP Necessity of W/Cu Divertor 2013-6-11525th SOFE, San Francisco US, June 10-14, 2013 L-Mode H-Mode The heating power will be rapid increased to  20MW

7 HT-7/ EAST ASIPP W/Cu Divertor Project  Divertor ITER-like configuration and structure, i.e., Monoblock targets (~10MW/m 2 ) and W Flat-type dome and baffler (3~5MW/m 2 )  First wall Mo +CVD-W or W flat type Max. heat flux capability 1~3MW/m 2  Schedule 2013-2014 W Udiv + C Ldiv + Mo (+ a new upper cryopump) 2015-2016 W div + Mo FW +W FW (depends) 2013-6-111625th SOFE, San Francisco US, June 10-14, 2013 Target: W monoblock FW: Mo tiles 2013 upper- div: W monoblock and flat-type 2013 low-div: Carbon tiles

8 HT-7/ EAST ASIPP Structure design – supports 2013-6-1125th SOFE, San Francisco US, June 10-14, 20137 Outer support Inner support Middle support Poster: TPO-110 Zibo Zhou

9 HT-7/ EAST ASIPP Structure design – PFUs/CB 2013-6-1125th SOFE, San Francisco US, June 10-14, 20138 Flat type W of ~2mm thick Compact end-boxes for cooling connects End-boxes End-box design Coolant from Cassette body Monoblock units ×4-5 Monoblock- W/Cu targets ~15,000 monoblocks 720 monoblock-units 240 flat-type mockups E-beam employed for CuCrZr welding

10 HT-7/ EAST ASIPP Structure design – CB assembly 2013-6-1125th SOFE, San Francisco US, June 10-14, 20139 Port number Cassette number Cassettes/ port PFUs/ cassette EAST168054/1/5 ITER1854316/34/22 Tolerance of plasma- facing surface: toroidal: 2mm; neighbor: 0.5mm

11 HT-7/ EAST ASIPP Structure design – cooling 2013-6-1125th SOFE, San Francisco US, June 10-14, 201310 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)

12 HT-7/ EAST ASIPP R & D for structure/assembly 2013-6-1125th SOFE, San Francisco US, June 10-14, 201311 VV simulator for assembly of supports + CBs

13 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 2013-6-111225th SOFE, San Francisco US, June 10-14, 2013

14 HT-7/ EAST ASIPP ITER-like Monoblock W/Cu PFMC 2013-6-1113 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

15 HT-7/ EAST ASIPP HIP+HIP/HRP HIP+HRP w/ 34 W-monoblocks ITER qualification mockup 2013-6-111425th SOFE, San Francisco US, June 10-14, 2013 =================================================== HIP+HIP EAST design

16 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. 2013-6-111525th SOFE, San Francisco US, June 10-14, 2013 HIP / VHP VPS / CVD VHP or gradient W/Cu layer

17 HT-7/ EAST ASIPP VPS/CVD-W & Castellation 2013-6-1125th SOFE, San Francisco US, June 10-14, 201316 W Cu VPS-W W Cu W/Cu interlayers CVD-W: WF 6 +3H 2 →W+6HF 0.3~0.5mm/h, porosity <1%, 99.999wt.% VPS-W: porosity 5-10%, 99.9wt%

18 HT-7/ EAST ASIPP High Heat Flux Testing 2015-5-517 A 60kW e-beam facility at SWIP Mockup by HIP + HRP 2013-6-111725th SOFE, San Francisco US, June 10-14, 2013

19 HT-7/ EAST ASIPP Thermal fatigue testing Heat load ~ 8.4MW/m 2, 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 ℃. 2013-6-111825th SOFE, San Francisco US, June 10-14, 2013 Cycle 1 Cycle 1000 Cycles 1-2 Cycles 999-1000

20 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. 2013-6-111925th SOFE, San Francisco US, June 10-14, 2013

21 HT-7/ EAST ASIPP Prototype Prototype of EAST divertor W/Cu armour was developed 2013-6-1125th SOFE, San Francisco US, June 10-14, 201320

22 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 2013-6-1125th SOFE, San Francisco US, June 10-14, 201321

23 HT-7/ EAST ASIPP 2013-6-1122 Thanks for your attention! 25th SOFE, San Francisco US, June 10-14, 2013

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