ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao

HT-7/ EAST ASIPP Presentation in fusion reactor division1 1.First Plasma 2.First water cooled PFC 3.Upgrade 4.Summary Outline

HT-7/ EAST ASIPP Presentation in fusion reactor division2 First Plasma The first plasma of EAST was obtained in 2006 with all plasma facing material is stainless steel 316L, except graphite poloidal limiter.

HT-7/ EAST ASIPP Presentation in fusion reactor division3 First Plasma

HT-7/ EAST ASIPP Presentation in fusion reactor division4 First Water cooled PFC

HT-7/ EAST ASIPP Presentation in fusion reactor division5 First Water cooled PFC

HT-7/ EAST ASIPP Presentation in fusion reactor division6 First Water cooled PFC

HT-7/ EAST ASIPP Presentation in fusion reactor division7 First Water cooled PFC Passive Stabilizer Active fast feedback VS coils

HT-7/ EAST ASIPP Presentation in fusion reactor division8 Molybdenum First Wall Mo FW + C Divrertor

HT-7/ EAST ASIPP Presentation in fusion reactor division9  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/m 2  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

HT-7/ EAST ASIPP Presentation in fusion reactor division10 Upgrade Background EAST Visible camera shows bright ELM structure Z (m) Major radius R (m)

HT-7/ EAST ASIPP Upgrade Background Presentation in fusion reactor division L-Mode H-Mode Power Density to Divertor

HT-7/ EAST ASIPP Design Objective Accommodate plasma configuration Module easy install and remove Strong enough for plasma event Heat load handling achieve 10MW/m 2 Enough conductance for pumping Apertures for diagnostics W/Cu Divertor Design

HT-7/ EAST ASIPP Presentation in fusion reactor division13 Structure design: EAST W/Cu divertor focus on ITER like structure and technology. W/Cu Divertor Design Flat type W of ~2mm thick End-boxes Monoblock- W/Cu targets Compact end-boxes for cooling connects

HT-7/ EAST ASIPP Presentation in fusion reactor division14 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 Monoblock structure End box

HT-7/ EAST ASIPP Presentation in fusion reactor division15 Monoblock design and optimization: W/Cu Divertor Design

HT-7/ EAST ASIPP Presentation in fusion reactor division16 Cooling water parameters optimization: W/Cu Divertor Design Inlet temperatureInlet velocity Outlet pressure

HT-7/ EAST ASIPP Presentation in fusion reactor division17 Cassette Design W/Cu Divertor Design Supports Pumping duct Cooling water circuit

HT-7/ EAST ASIPP Presentation in fusion reactor division18 Cassette Structure analysis: Input data: Halo current Ih=25%Ip and TPF=2, Eddy current calculated by COMSOL code. W/Cu Divertor Design

HT-7/ EAST ASIPP Presentation in fusion reactor division19 Divertor Development Monoblock Development---HIP Plasma facing surface perpendicular To W material rolling direction

HT-7/ EAST ASIPP Presentation in fusion reactor division20 W/Cu divertor R&D W/Cu Divertor Development Monoblock target Prototype of Divertor module

HT-7/ EAST ASIPP Presentation in fusion reactor division21 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

HT-7/ EAST ASIPP Presentation in fusion reactor division22 Divertor Development 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 ℃. Cycle 1 Cycle 1000 Cycles 1-2 Cycles

HT-7/ EAST ASIPP Presentation in fusion reactor division23 Divertor Development Flat Type Development HIP / VHP VPS / CVD VHP or gradient W/Cu layer HIP

HT-7/ EAST ASIPP Presentation in fusion reactor division24 Divertor Development HIP Flat Type Testing 5MW/m 2 ; 15s on & 15s off NDT result after 1001 cycles

HT-7/ EAST ASIPP Presentation in fusion reactor division25 VS coils relocation Position 1 Current Position Old position Position 3

HT-7/ EAST ASIPP Presentation in fusion reactor division26 VS coils Development VS coils conductor: ITER like conductor technology ： Pure copper conductor with water cooling, MgO powder insulation, SS jacket SS316L Jacket MgO Powder Pure Copper

HT-7/ EAST ASIPP Presentation in fusion reactor division27 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.

HT-7/ EAST ASIPP Presentation in fusion reactor division28 RMP coils Design 3D view of the coil system with plasma configuration. 2D view of the coil system in poloidal cross section

HT-7/ EAST ASIPP Presentation in fusion reactor division29 RMP coils Design Functions and parameters of RMP Coils FunctionPulsest(s)/Pulset_total(s)CurrentFrequence(Hz) Error field correction kAt0 ELM control kAt 0(80%),50(20 %) RWM Control kAt<= 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.

HT-7/ EAST ASIPP Presentation in fusion reactor division30 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

HT-7/ EAST ASIPP Presentation in fusion reactor division31 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.

HT-7/ EAST ASIPP Presentation in fusion reactor division32 Second Cryo-pump Cryo-pump Design The 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.

HT-7/ EAST ASIPP Presentation in fusion reactor division33 Second Cryo-pump Cryo-pump manufacturing Installation The cryo-pump design nominal pumping speed is127m 3 /s, and effective pumping speed is 37m 3 /s (for N 2 ), effective pumping speed for D 2 is ~80m 3 /s, for H 2 is ~110m 3 /s

HT-7/ EAST ASIPP Presentation in fusion reactor division34 Summary Full C PFC Mo FW + C Divrertor First Plasma 2014 Mo FW+W&C Divertor

HT-7/ EAST ASIPP Presentation in fusion reactor division35 Summary RMP coils Upper Divertor Upper Cryo-pump VS coils

HT-7/ EAST ASIPP Presentation in fusion reactor division36 Summary

HT-7/ EAST ASIPP Summary Presentation in fusion reactor division37  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/m 2 for steady state and 15MW/m 2 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

HT-7/ EAST ASIPP Thanks for your attention! Presentation in fusion reactor division