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Design Of EAST Upgraded In Vessel Components

Design Of EAST Upgraded In Vessel Components. Presented by Damao Yao 9 th APFA November 05-08, 2013, Gyeongju, Korea. Outline. Background W/Cu Divertor Design VS coils design and relocation RMP coils design Second Cryopump Summary. Outline. Background W/Cu Divertor Design

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Design Of EAST Upgraded In Vessel Components

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  1. Design Of EAST Upgraded In Vessel Components Presented by Damao Yao 9th APFA November 05-08, 2013, Gyeongju, Korea

  2. Outline • Background • W/Cu Divertor Design • VS coils design and relocation • RMP coils design • Second Cryopump • Summary APFA 2013 Korea

  3. Outline • Background • W/Cu Divertor Design • VS coils design and relocation • RMP coils design • Second Cryopump • Summary APFA 2013 Korea

  4. Background • The EAST plasma heating power is updating to 20MW with LHCD 10MW, ICRH 8MW and NBI2MW, 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 APFA 2013 Korea

  5. Background Z (m) 0 -0.5 2 2.25 EAST #41019@3034ms Visible camera shows bright ELM structure Major radius R (m) APFA 2013 Korea

  6. Background Power Density to Divertor L-Mode H-Mode APFA 2013 Korea

  7. Outline • Background • W/Cu Divertor Design • VS coils design and relocation • RMP coils design • Second Cryopump • Summary APFA 2013 Korea

  8. W/Cu Divertor Design Compact end-boxes for cooling connects Monoblock- W/Cu targets End-boxes End-boxes Flat type W of ~2mm thick Structure design: EAST W/Cu divertor focus on ITER like structure and technology. APFA 2013 Korea

  9. W/Cu Divertor Design End box W Monoblock structure Flat W/Cu with cooling channel W target design: Tungsten plasma facing target design as monoblock structure for vertical target and flat structure for baffle. APFA 2013 Korea

  10. W/Cu Divertor Design Monoblock design and optimization: APFA 2013 Korea

  11. W/Cu Divertor Design Inlet temperature Inlet velocity Outlet pressure Cooling water parameters optimization: APFA 2013 Korea

  12. W/Cu Divertor Design Pumping duct Supports Cooling water circuit Cassette Design APFA 2013 Korea

  13. W/Cu Divertor Design Cassette Structure analysis: Input data: Halo current Ih=25%Ip and TPF=2, Eddy current calculated by COMSOL code. APFA 2013 Korea

  14. Divertor Development Monoblock Development---HIP Plasma facing surface perpendicular To W material rolling direction APFA 2013 Korea

  15. W/Cu Divertor Development Prototype of Divertor module Monoblock target W/Cu divertor R&D APFA 2013 Korea

  16. Divertor Development Defects > f2mm 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 Spiral scanning ultrasonic NDT of W/Cu interface APFA 2013 Korea

  17. Divertor Development Cycles 1-2 • 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℃. Cycles 999-1000 Cycle 1 Cycle 1000 APFA 2013 Korea

  18. Divertor Development Flat Type Development HIP HIP / VHP VPS / CVD or gradient W/Cu layer VHP APFA 2013 Korea

  19. Divertor Development 5MW/m2; 15s on & 15s off HIP Flat Type Testing • NDT result after 1001 cycles APFA 2013 Korea

  20. Outline • Background • W/Cu Divertor Design • VS coils design and relocation • RMP coils design • Second Cryopump • Summary APFA 2013 Korea

  21. VS coils relocation Position 1 Current Position Old position Position 3 APFA 2013 Korea

  22. VS coils Development VS coils conductor: ITER like conductor technology： Pure copper conductor with water cooling, marmag powder insulation, SS jacket SS316L Jacket MgO Powder Pure Copper APFA 2013 Korea

  23. 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. APFA 2013 Korea

  24. Outline • Background • W/Cu Divertor Design • VS coils design and relocation • RMP coils design • Second Cryopump • Summary APFA 2013 Korea

  25. RMP coils Design 3D view of the coil system with plasma configuration. 2D view of the coil system in poloidal cross section APFA 2013 Korea

  26. RMP coils Design Functions and parameters of RMP Coils APFA 2013 Korea

  27. 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 APFA 2013 Korea

  28. 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. APFA 2013 Korea

  29. Outline • Background • W/Cu Divertor Design • VS coils design and relocation • RMP coils design • Second Cryopump • Summary APFA 2013 Korea

  30. 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. APFA 2013 Korea

  31. 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 APFA 2013 Korea

  32. Outline • Background • W/Cu Divertor Design • VS coils design and relocation • RMP coils design • Second Cryopump • Summary APFA 2013 Korea

  33. Summary 2010 2012 Mo FW + C Divrertor 2014 Full C PFC First Plasma Mo FW+W&C Divertor APFA 2013 Korea

  34. Summary Upper Cryo-pump Upper Divertor RMP coils VS coils APFA 2013 Korea

  35. Summary • 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 ITERlike 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 APFA 2013 Korea

  36. Thanks for your attention! APFA 2013 Korea

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