Fusione nucleare e progetto ITER

Transcript

1 Fusione nucleare e progetto ITER - Sergio Orlandi PED Department Head Page 1

2 ITER Fusion Technology Comes of Age Page 2

3 Presentation overview Organizational reform Update on manufacturing and construction Physics research and engineering innovation Page 3

4 A staged approach to DT plasma Extensive Extensive interactions interactions among among IO IO and and DAs DAs to to finalize finalize revised revised baseline baseline schedule schedule proposal proposal Schedule Schedule and and resource resource estimates estimates through through First First Plasma Plasma (2025) (2025) consistent consistent with Members with Members budget budget constraints constraints Proposed Proposed use use of 4-stage of 4-stage approach approach through through Deuterium-Tritium Deuterium-Tritium (2035) consistent (2035) consistent with with Members Members financial financial and and technical technical constraints constraints Page 4

5 Major Assembly Milestones Page 5

6 Assembly Hall PF Coil winding facility Radiofrequency Heating Cryostat workshop Cryoplant Service Building 400 kv Switchyard Cooling water sys. Magnet Power Conversion Bdgs. Tritium Building Thursday, 13 April 2017 Tokamak Building Diagnostics Building Worksite Construction progress Page 6

7 Tokamak Complex Resting on 493 seismic pads, the ton Tokamak Complex comprises 7 levels (2 underground). Page 7

8 Tokamak Complex Resting on 493 seismic pads, the ton Tokamak Complex comprises 7 levels (2 underground). Page 8

9 Assembly Hall Before being integrated in the machine, the components will be prepared and pre-assembled in this 6,000 m2, 60-metre high building. The Assembly Hall is equipped with a double overhead travelling crane with a total lifting capacity of 1,500 tons. Page 9

10 Assembly Hole Sector sub-assembly tools In Korea, factory assembly phase for sector sub-assembly tools is completed. Page 10

11 Cooling Water System ITER power will be partly evacuated by cooling towers (procured by India). Work on the hot and cold basins foundations began in August. Page 11

12 Cryoplant Steel structure installation is ongoing on what will be the largest single platform cryoplant in the world. The ITER Cryoplant will distribute liquid helium to various machine components (supraconducting magnets, thermal shield, cryopumps, etc.). Page 12

13 Magnet power conversion Foundation works and column construction are ongoing in the two large Magnet Power Conversion buildings that will host the AC/DC converters feeding power to the ITER magnets. Page 13

14 Electrical network The connection to the RTE 400 kv network was successfully tested on 30 March. Page 14

15 PF Coil winding facility Too large to be transported by road, four of ITER s six ring-shaped magnets (the poloidal field coils, 8 to 24 m in diametre) will be assembled by Europe in this 12,000 m² facility. The first real DP for PF5 (17 m. in diameter) is now being wound in the PF Coil Winding Building. Page 15

16 Cryostat workshop Manufactured in India, the 30 m x 30 m cryostat (the insulating vacuum vessel that encloses the machine) is being assembled and welded on site. Welding operations for the base section (1 250 t.) is complete; verification of welds helium test and radiography) are ongoing. Page 16

17 Entering the industrial phase with highly challenging specifications Manufacturing of ITER components is taking place at the cutting edge of technology: Geometrical tolerances measured in millimetres for steel pieces up to 17 m tall weighing several tons Superconducting power lines cooled to minus 270 degrees Celsius Plasma facing components to withstand heat flux as large as 20 MW per m 2 Cryoplant cooling capacity up to 110 kw at 4.5 K; maximum cumulated liquefaction rate of 12,300 litres/hr Etc. Page 17

18 The ITER TOKAMAK and Vacuum Vessel A multinational scientific collaboration A large-scale experiment to demonstrate FEASIBILITY of FUSION ENERGY R=6.2 m, a=2.0 m, I p =15 MA, B T =5.3 T, 23,000 tonnes Q=10 Page 18

19 The ITER Vacuum Vessel A torus shaped double wall structure To provide high vacuum for plasma and primary radioactivity confinement boundary To support in-vessel components (blanket, divertor, etc.) Upper Main vessel 9 x 40 deg. Sector Equatorial Lower In-wall shield Major dimensions Weight (ton) Outer diameter (m) 19.4 Main vessel 1611 Height (m) 11.4 Shielding 1733 Double wall thickness (m) Ports 1781 Interior surface (m 2 ) 850 Supports 111 Interior volume (m 3 ) 1600 Total 5236 Ports VV supports (Dual hinge type) Page 19

20 Procurement Arrangements EU Description Items 5 Sectors of Main Vessel RF Items Description 18 Upper Ports Total kiua KO Description IN Description Items 4 Sectors of Main Vessel 17 Eq. & 9 Lower Ports Items In-Wall Shields/ribs Page 20

21 Assembly configuration of VV and TF Magnets Sub-assembly of VV sector + 2 TF coils Assembly configuration of 9 VV sectors + 18 TF coils Assembly at the Pit Page 21

22 Integration of the VV and IVCs BLANKET MODULES MANIFOLD DIVERTOR INTERNAL COILS INTERFACES Page 22

23 EU Sector Manufacturing The first sector #5 is at sub poloidal segment (PS) manufacturing stage (35 %) PS1 : Machining of Inner Shell PS2 : Sub-assemblies PS3 : Machining of port flanges PS4 : Welding of triangular support Page 23

24 KO Sector Manufacturing The first sector #6 is at poloidal segment manufacturing stage (65 %) PS1 : Inspection of Support Ribs for IWS PS2 : Fit-up of T-ribs to Inner Shell PS3 : Welding of T-ribs to Inner Shell PS4 : Welding of port stub Page 24

25 Design and Qualifications of VV Assembly VV assembly is design and qualification stage Set 1 and 2 Mock-ups 1:1 Sector mock-up 1:1 HNB-DNB Port mock-up 1:1 Upper Port mock-up Page 25

26 Summary All Procurement Arrangements have been signed until The ITER Vacuum Vessel is under manufacturing phase with 4 Domestic Agencies, European Union, Korea, Russian Federation, and India from Assembly of the VV is under design and qualification phase. Main components of the VV such as sectors and ports are being manufactured. All manufacturing design have been completed and approved by the IO and ANB. All manufacturing qualifications such as forming, welding, and nondistructive tests, have been completed. All materials have been procured and most of them are delivered. Manufacturing speed is accelerated in 2017 after major qualifications achieved. Sector delivery dates have been updated with resource loaded plans. Page 26

27 Manufacturing Progress The first resin impregnated toroidal field coil winding pack was completed at ASG in La Spezia, Italy. Quench tanks for the ITER cryoplant have been delivered to the site. Buildings, Magnet Systems, Heating & Current Drive Systems, Vacuum Vessel, Divertor, Blanket, Power Systems, Fuel Cycle, Tritium Plant, Cryoplant, Diagnostics, Radioactive Materials Page 27

28 Manufacturing Progress The manufacturing of the Full-scale Divertor Cassette Body Prototype is well advanced. Part of the 35m transmission line connected to the SPIDER vessel at the Neutral Beam Testing Facility (NBTF) site in Padua, Italy. Buildings, Magnet Systems, Heating & Current Drive Systems, Vacuum Vessel, Divertor, Blanket, Power Systems, Fuel Cycle, Tritium Plant, Cryoplant, Diagnostics, Radioactive Materials Page 28

29 Engineering innovation: Superconductors 200 km, 2,800 tons of superconductors (90% of the total required) have been manufactured and validated Six ITER Members China, Europe, Japan, Korea, Russia and the United States have been responsible for the production of cable-in-conduit conductors worth a total of EUR 610 million. The eight-year campaign to produce the superconductors for ITER s powerful magnet systems is in its final stages. *Harmonized global standards for production methods, quality controls, testing protocols, etc. *Groundbreaking work in materials science. *Largest superconductor procurement in industrial history. Page 29

30 Engineering innovation: Vacuum Systems 8-tonne machined flange of the first Torus Cryo-pump Neutral Beam Injection Cryo-pump: 8 meters long, 2.8 meters high The ITER vacuum system will be one of the largest, most complex vacuum systems ever built: the cryostat, at ~ 8500m3; the torus, at ~1330 m3; the neutral beam injectors at ~180m3 each; plus lower volume systems. More than 400 vacuum pumps will employ 10 different technologies. Final design involved new fabrication methods to reduce cost and manufacturing time of cryo-panels and thermal shields within the pumps. Torus and Cryostat Cryo-pump (1.8 m. diameter) Page 30

31 Engineering innovation: Robotics and Remote Handling Due to the massive size of the ITER Tokamak components, as well as the intense neutron flux that will occur during operations, the ITER machine has required the development of cutting-edge robotics and remote handling tools, which will be used in both the assembly and operational phases. Page 31

32 Innovation: other aeras Pellet fueling & ELM Pacing Power electronics High technology filters Explosive forming Ultrahigh speed signal transmission (TeraHertz) Etc. Page 32

33 ITER Cooling Water System (CWS) The ITER Cooling Water System (CWS) is designed to control the main thermal hydraulic parameters of the systems (e.g. in-vessel Components and Power Supplies) and to reject their heat loads to the environment when the plasma will be heated at 50 MW and the D-T fusion power heat will reach 500 MW with an amplification factor Q 10. In that condition, CWS shall remove a peak heat load of about 1150 MW. The CWS is divided in: Tokamak Cooling Water System (TCWS) Primary closed circuits; Component Cooling Water System (CCWS) Secondary closed circuits; Chilled Water System (CHWS) Secondary closed circuits; Heat Rejection System (HRS) Tertiary open circuit. Page 33

34 Cooling Water System (CWS) at ITER site IN-ITER scope of design and procurement for CCWS, CHWS and HRS piping (mainly outside buildings) Length of piping [km] Weight of piping [kn] Piping support weight [kn] Valves [pieces] IN-ITER scope of design and optional procurement for CCWS, CHWS and HRS piping (only inside buildings) Length of piping [km] Weight of piping [kn] Piping support weight [kn] Valves [pieces] CCWS-2C Build. 38 CCWS-2B Build. 32 CCWS-1 Build HRS Build CCWS-2D Build. 50s Water Inventory CCWS-1 CCWS-2 A CCWS-2 B CCWS-2 C CCWS-2 D CHWS-H1 CHWS-H2 HRS 25,000 m m3 310 m3 390 m3 45 m m3 350 m3 680 m3 TCWS Build CCWS-2A Build. 15 An CHWS-H2 Build. 61 Page 34

35 Heat Rejection System (HRS) HRS special design imposed by the pulsed nature of ITER operations; HRS heat rejection capacity fluctuates from 1150 to 150 MW; Two separate water hot/cold basins (10,000 m3 each) to dump the peak heat load by thermal capacity; Cold basin collects the water from the Cooling Towers (CTs); The VTR pumps for CCWS-1 provided with variable speed drives (VFDs); CTs average nominal capacity 510 MW. Page 35

36 ITER Heat Rejection System (HRS) 1,800 m of pipes > DN1000 2,200 m of pipes DN25-DN Cooling Water Tower Cells 23 circulation pumps 18 heat exchangers 2 pressurizer tanks 1 dosing equipment 6 Motor Control Centers 8 Control Cubicles 30 km of cables Page 36

37 Tokamak Cooling Water System (TCWS) TCWS InCryostat length 13.0 km Out Cryostat length 21.5 km Total length 34.5 km Number of valves 2900 Weight of piping 6000 kn Weight of valves & sup kn Total Weight 7740 kn TCWS Water Inventory VV PHTS 322 m3 IBED PHTS 470 m3 NBI PHTS 72 m3 Total vol. 984 m3 Page 37

38 TCWS inside Tokamak Complex (upper view) Penetration inside Bioshield and Cryostat IBED PHTS CVCS NBI PHTS IBED PHTS Upper pipe chase distribution DYS Page 38

39 VV PHTS and DRS inside Drain Tank room PHTS Safety Drain Tank PHTS Normal Drain Tank VV PHTS NBI Drain Tank Waste Collection Tank Page 39

40 Status of the delivery of CWS captive piping Temporary storage of CCWS-CHWS and HRS captive piping Three Lots; Total 1073 spools (740 cs ss); 864 already delivered at ITER site; DN mm; L 6500 m (4600 m cs m ss); PED cat. : SEP ( DN < 350 mm); PED cat. : I ( DN >= 350 mm). Page 40

41 Status of the delivery of CWS equipment Ozonator system for HRS to be installed in Building 64 Page 41

42 TCWS phased approach 1 st Plasma: VV-PHTS; DYS; DRs; Captive piping. 2 nd Plasma: Full TCWS Page 42

43 TCWS captive Drain Tanks storage at ITER Site PHTS Drain Tank Vol 232 m3 OD 6500 x H 9300 mm Dry Weight 73 ton NBI Drain Tank Vol 110 m3 OD 6500 x H 5300 mm Dry Weight 47 ton Page 43

44 Progress in the CWS installation on ITER Site. Progress on May 2017 Page 44

45 ITER is moving forward! Page 45

48 Thank you for your attention Page 48