1. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 1 De sign, Fabrication and Testing of the ITER First Wall and Shielding Blanket Presented by A. René Raffray Blanket Section Leader; Blanket Integrated Product Team Leader ITER Organization, Cadarache, France With contributions from B. Calcagno 1, P. Chappuis 1, G. Dellopoulos 2, R. Eaton 1, Zhang Fu 1, A. Gervash 6, Chen Jiming 3, D-H. Kim 1, S-W.Kim 4, S. Khomiakov 5, A. Labusov 6, A. Martin 1, M. Merola 1, R. Mitteau 1, M. Ulrickson 7, F. Zacchia 2 and all BIPT contributors 1 ITER Organization; 2 F4E, EU ITER Domestic Agency; 3 SWIP, China ITER Domestic Agency; 4 NFRI, ITER Korea; 5 NIKIET, RF ITER Domestic Agency; 6 Efremov, RF ITER Domestic Agency; 7 SNL, US ITER Domestic Agency; 11 th International Symposium on Fusion Nuclear Technology, Barcelona, Spain, Sept. 16-20, 2013 The views and opinions expressed herein do not necessarily reflect those of the ITER Organization

2. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 2 Blanket Effort Conducted within BIPT Blanket Integrated Product Team ITER Organization DA’s - CN - EU - KO - RF - US Include resources from Domestic Agencies to help in major design and analysis effort. Direct involvement of procuring DA’s in design -Sense of design ownership -Would facilitate procurement

3. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 3 Blanket System Functions Main functions of ITER Blanket System: Contribute in absorbing radiation and particle heat fluxes from the plasma Contribute in providing shielding to reduce heat and neutron loads in the vacuum vessel and ex-vessel components Provide a plasma-facing surface which is designed for a low influx of impurities to the plasma Provide limiting surfaces that define the plasma boundary during startup and shutdown Provide passage for the plasma diagnostics

4. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 4 Modules 1-6 Modules 7-10 Modules 11-18 ~850 – 1240 mm SB (semi-permanent) FW Panel (separable) Blanket Module Blanket System The Blanket System consists of Blanket Modules (BM) comprising two major components: a plasma facing First Wall (FW) panel and a Shield Block (SB). 50% 40% 10% SB Attachment to VV 100%

5. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 5 Blanket System in Numbers Number of Blanket Modules: 440 Max allowable mass per module:4.5 tons Total Mass: 1530 tons First Wall Coverage: ~600 m 2 Materials: -Armor:Beryllium -Heat Sink:CuCrZr -Steel Structure:316L(N)-IG -Axial attachment (bolt/cartridge)Alloy 718 -PadAl Bronze -Insulating layerAlumina Max total thermal load:736 MW Cooling water conditions: 4 MPa and 70°C

6. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 6 Impact of Interface Requirements on Blanket Design Interface requirements impose challenging demands on the blanket in particular since the blanket is in its pre-PA phase whereas several major interfacing components are already in procurement. Such demands include: -Accommodating plasma heat loads on FW -Maintaining acceptable load transfer to the vacuum vessel -Providing sufficient shielding to the vacuum vessel and TF coils -Accommodating the space allocations for in-vessel coils, manifolds and plasma heating systems. These are highlighted in subsequent slides as part of the blanket design description.

7. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 7 The blanket is a major contributor to neutron shielding of the coils and vacuum vessel. e.g. to enhance shielding, blanket-related modifications were introduced following PDR: -a flat inboard profile -an addition of 4 cm to mid-plane radial thickness -a reduction of the vertical gaps between inboard SB’s from 14 to 10 mm. This has resulted in lowering the integrated heating in the coil to from 17 to 15.7 kW (as compared to a target of 14 kW) Inboard Module Shape and Size Optimized for Neutron Shielding of VV and TF Coil An assessment indicates that this could still allow fusion power close to the design value of 500MW for a 1800s rep period without any adjustment of the cryo-plant operating conditions.

8. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 8 I-shaped beam to accommodate poloidal torque Design of First Wall Panel Impacted by Accommodation of Plasma Interface Requirements

9. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 9 Plasma RH access Exaggerated shaping -Allow good access for RH -Shadow leading edges Shaping of First Wall Panel Heat load associated with charged particles is a major component of heat flux to first wall. The heat flux is oriented along the field lines. Thus, the incident heat flux is strongly design-dependent (incidence angle of the field line on the component surface). Shaping of FW to shadow leading edges and penetrations.

10. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 10 Plasma Loads to the First wall -Combination of steady-state and off-normal loads -Design based on steady-state loads and maximum armor thickness -Beryllium surface damage accepted during off-normal events -Learn from early operation before moving to higher power scenarios to minimize off- normal events with major impact on FW armor lifetime

11. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 11 First Wall Panels: Design Heat Flux 218 Normal heat flux panels  EU 222 Enhanced heat flux panels  RF, CN

12. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 12 Normal Heat Flux (NHF) First Wall CuCrZr Alloy SS Pipes Be tiles SS Back Plate Normal Heat Flux Semi-Prototype Normal Heat Flux Finger: q’’ = 2 MW/m 2 Steel Cooling Pipes HIP’ing

13. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 13 Enhanced Heat Flux (EHF) First Wall Enhanced Heat Flux Finger: q’’ = 4.7 MW/m 2 Hypervapotron Explosion bonding (SS/CuCrZr) + brazing (Be/CuCrZr) Be tiles Bimetallic structure CuCrZr/SS 316L(N)-IG Finger body (Steel 316L(N)- IG) Coolant channel lid (Steel 316L(N)-IG) Hypervapotron (HVT) Central welding External welding Brazing Laser welding EHF FW Semi-Prototype

14. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 14 Shield Block Design Slits to reduce EM loads and minimize thermal expansion and bowing Cooling holes are optimized for Water/SS ratio (Improving nuclear shielding performance). Cut-outs at the back to accommodate many interfaces (Manifold, Attachment, In-Vessel Coils).

15. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 15 Shield Block Full-Scale Prototypes KODA: SB08 CNDA: SB14 (example of some processes) Basic fabrication method from a single high-quality forged steel block and includes drilling of holes, welding of cover plates for water headers, and final machining of the interfaces.

16. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 16 Shield Block Attachment 4 flexible axial supports Keys to take moments and forces Electrical straps to conduct current to vacuum vessel e.g. BM 4 Interfaces MANIFOLD FLEXIBLE CARTRIDGE INTERMODULAR PADS SHIELD BLOCK FIRST WALL ELECTRICAL STRAPS (SB & FW) CENTERING PADS

17. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 17 Flexible Axial Support 4 flexible axial supports located at the rear of SB, where nuclear irradiation is lower. Compensate radial positioning of SB on VV wall by means of custom machining. Cartridge and bolt made of high strength Alloy-718 Designed for 800 kN preload to take up to 600 kN Category III load. FSP for testing (NIKIET, RF)

18. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 18 Keys in Inboard and Outboard Modules to Accommodate Moments and Forces from EM Loads Each inboard SB has two inter-modular keys and a centering key to react the toroidal forces. Each outboard SB has 4 stub keys concentric with the flexible supports. Bronze pads are attached to the SB and allow sliding of the module interfaces during relative thermal expansion. Key pads are custom-machined to recover manufacturing tolerances of the VV and SB.

19. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 19 Pads and Insulating Layer Pads moved to Shield Block to minimize impact on VV interfaces Electrical insulation of the pads through ceramic coating on their internal surfaces. Cylindrical pads for IMK; rectangular pads for stub keys Insulating layer performance determined by R&D (8000 cycles at 1.5 MN and 1 run at 2 MN)) Scheme of Testing Test Samples: Al-bronze, plasma sprayed Al2O3 Inter-Modular Key pads on Inboard

20. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 20 Shield Block and Attachment Designed to Respect Pre- Defined Load from Vacuum Vessel Load Specifications Optimizing blanket design (radial thickness and slitting) to reduce EM loads based on the following analysis: -DINA analysis of disruptions and VDEs -Eddy and halo analysis to obtain superposition of wave forms -Dynamic analysis of BM structural response using ANSYS (NIKIET) For example, results for BM 1 (one of the most loaded modules) show that the loads on the keys are within the VV LS for Cat. II and Cat. III cases

21. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 21 Interface with Blanket Manifold and In-Vessel Coils A multi-pipe manifold configuration has been chosen, with each pipe feeding one or two BM’s -Higher reliability due to minimization of welds and utilization of seamless pipes. -Superior leak localization capability due to larger segregation of cooling circuits. -Elimination of drain lines. In-Vessel coils: three sets of ELM control coils per outboard sector to control ELMs by applying an asymmetric resonant magnetic perturbation to the plasma surface and 2 sets of vertical stability (VS) coils for plasma stabilization. BMs to be designed with cut-outs to accommodate these space reservations. Multi-pipe Manifold Configuration Example outboard SB 12 with manifold and ELM coil cut-outs ELM coils VS coils

22. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 22 Interface with Neutral Beam System The NB region with the neutron bean injection ports create a particular geometry challenge for the blanket design Special modules have been developed to accommodate this as well as the other design constraints The NB shine-through also needs to be accommodated by the impacted Blanket Modules

23. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 23 FW 16 to Accommodate Neutral Beam Shine- Through Detailed Model done following EHF FW guidelines (central-slot insert not shown here for simplicity). Special shaping to accommodate shine-though beam and protect slot. Analysis assessment performed to verify stress compliance with SDC-IC (ITER structural design criteria) for both M-type (monotonic) and C-type (cyclic) damage.

24. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 24 Supporting R&D A detailed R&D program has been planned in support of the design, covering a range of key topics, including: -Critical heat flux (CHF) tests on FW mock-ups. -Experimental determination of the behavior of the attachment and insulating layer under prototypical conditions. -Material testing under irradiation. -Demonstration of the different remote handling procedures. A major part of the R&D effort is the qualification program for the SB and FW panels. -Full-scale SB prototypes (KODA and CNDA). -FW semi-prototypes (EUDA for the NHF FW Panels, and RFDA and CNDA for the EHF First Wall Panels). -Qualification tests include: He leak test, pressure test, FW heat flux test

25. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 25 Procurement Schedule ComponentSMP PA Start/End Date* Blanket First Wall RFDA CNDA EUDA Nov-2013 / Dec-2020 Sept-2014 / July-2020 Dec-2014 / Feb-2021 Blanket Shield Block CNDA KODA Nov-2013 / Feb-2021 Nov-2013 / Oct-2020 Blanket Module Connectors RFDAJuly-2014 / Jan-2020 -FDR: April 2013 (successfully held) -FDR Approval: July 2013 (ahead of schedule) *End date = delivery of last component to ITER site

26. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 26 Summary The Blanket design is extremely challenging, having to accommodate high heat fluxes from the plasma, large EM loads during off-normal events and demanding interfaces with many key components (in particular the VV and IVC) and the plasma. Substantial re-design following the ITER Design Review of 2007. The Blanket CDR, PDR and FDR have confirmed the correctness of this re-design. Effort now focused on finalizing the design work based on input received at the FDR and to prepare for procurement starting at the end of 2013. Parallel R&D program and DA pre-qualification process by the manufacturing and testing of full-scale or semi-prototypes.

27. ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 27 Latest Blanket Major Milestone Blanket FDR successfully held in April 2013