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

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

HT-7/ EAST ASIPP PFC for EAST th 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

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

HT-7/ EAST ASIPP Necessity of W/Cu Divertor th 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 SN

HT-7/ EAST ASIPP Necessity of W/Cu Divertor th SOFE, San Francisco US, June 10-14, 2013 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/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 W Udiv + C Ldiv + Mo (+ a new upper cryopump) W div + Mo FW +W FW (depends) th 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

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

HT-7/ EAST ASIPP Structure design – PFUs/CB th SOFE, San Francisco US, June 10-14, 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

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

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

HT-7/ EAST ASIPP ITER-like Monoblock W/Cu PFMC 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 th SOFE, San Francisco US, June 10-14, 2013 =================================================== HIP+HIP EAST 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 th SOFE, San Francisco US, June 10-14, 2013 HIP / VHP VPS / CVD VHP or gradient W/Cu layer

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

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

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 ℃ th SOFE, San Francisco US, June 10-14, 2013 Cycle 1 Cycle 1000 Cycles 1-2 Cycles

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

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

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

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