INFORMATION DAY. Fusion for Energy (F4E)

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1 INFORMATION DAY 26th November 2013, Zagreb Fusion for Energy (F4E) Part 2 Status of the ITER Project and Achievements Jesus Izquierdo Technical Coordination and Integration 1

2 THE ITER PROJECT MAIN SYSTEMS EU PACKAGES R&D, prototyping, transfer of technology, innovative design, new fabrication procedures, qualification of materials and processes... Up to design, manufacturing, installation and commissioning of the ITER European Procurement Packages. Buildings Construction Site Vacuum Vessel Superconducting Magnets In-vessel Components Remote Handling Cryoplant and Fuel Cycle Heating and Current Drive Diagnostics TBS Manufacturing Design 2

3 THE ITER PROJECT MAIN SYSTEMS - TOKAMAK 840 m 3 plasma, C, part/m 3, 500 MW In-vessel components (BLANKETS, DIVERTOR) VACUUM VESSEL (9 sectors) TOROIDAL FIELD COILS (18 coils, 4 K) POLOIDAL FIELD COILS (6 coils, 4 K) CENTRAL SOLENOID (6 modules, 4 K) THERMAL SHIELDS (80 K) CRYOSTAT CRYOPUMPS PLASMA HEATING (Radiofrequency EC & IC, Neutral Beam Injectors) PLASMA FUELLING (pellets, puffing) DIAGNOSTICS (plasma measurements) REMOTE HANDLING 3

4 THE ITER PROJECT MAIN SYSTEMS - PLANT SYSTEMS 4

5 ITER CURRENT STATUS 5

6 ITER CONSTRUCTION SITE Headquarters building ITER foundations Coil manuf. building Seismic isolation pit 6

7 ITER TOKAMAK VACUUM VESSEL Building the ITER Vacuum Vessel A complex and huge vacuum vessel is used to contain the hot plasma Made of a double shell 60 mm thick of stainless steel 316 LN, according to nuclear codes Made up of nine sectors like the slices of an orange When all the sectors are joined, it will weigh more than 5000 tonnes About to be pressed into shape Welding Pieces Together 7

8 ITER TOKAMAK VACUUM VESSEL Each 40 sectors, approx. 6.5x6.5x11 m, 400 tons weight including in-wall shielding The 60 mm shells have double curvature. Tolerances in the range of ±10mm on shell surfaces and ±2mm on interface areas: maximizing 3D hot forming Maximizing Electron Beam Welding (low heat input techniques) Full penetration welds and 100% volumetric inspection (NDT programs!) VV Mock-ups (AWM) 8

9 ITER TOKAMAK MAGNETS Building the ITER Magnets Magnets hold the hot plasma and refrain it from touching the walls of the vacuum vessel To reduce power loss from magnets, special superconducting cable is used Europe is building most of the largest ITER magnets Spool of cable Cables wrapped into shape Cable is wrapped around a D-shape 9

10 ITER TOKAMAK IN-VESSEL COMPONENTS FIRST WALL Electrical straps Inlet pipe Central bolt location Rear side view Outlet pipe FW to SB pads Hydraulic connection between adjacent fingers 440 shield blanket modules FW surface: 680 m 2 Be tiles CuCrZr SS pipes SS hollow structure ITER FW covered by 2 designs: Normal Heat Flux (NHF) (< 2 MW/m 2 ) and Enhanced Heat Flux (EHF) (2.1 to 4.6 MW/m 2 ). NHF Finger 3D view 10

11 ITER TOKAMAK IN-VESSEL COMPONENTS FIRST WALL HIPped fabrication route selected by the EUDA for the manufacture of FW panels 316L SS / CuCrZr joining 316L Stainless Steel / CuCrZr alloy HIP joining 1040 C, 140 MPa, 2 hrs Post HIP Solution Annealing HT with fast cooling CuCrZr / Beryllium joining 580 C, 140 MPa, 2 hrs CuCrZr alloy / Beryllium HIP joining Three full scale FW panel prototypes with HIPped Be tiles completed One full scale FW panel prototype with brazed Be tiles completed Full scale FW panel prototypes 11

12 ITER TOKAMAK IN-VESSEL COMPONENTS DIVERTOR Inner Vertical Target (IVT) Outer Vertical Target (OVT) Dome (DO) Cassette Assembly ~ 7.9 tons Cassette Body ~ 4.7 tons 12

13 ITER TOKAMAK IN-VESSEL COMPONENTS DIVERTOR Tungsten Qualification Programme Technology Development and Validation: With full-w small-scale mock-ups; Full-scale feasibility demonstration: with full-scale prototype manufacturing and testing. HHF tests for small-scale and full-scale prototype straight part 5000 cycles at 10 MW/m cycles at 20 MW/m 2 HHF test for prototype curved part 5000 cycles at 5 MW/m 2 Full-scale IVT prototype 13

14 ITER TOKAMAK IN-VESSEL COMPONENTS DIVERTOR Simulation of Remote Integration of Divertor system ALCA TECHNOLOGY 14

15 ITER SYSTEMS REMOTE HANDLING 15

16 ITER SYSTEMS FUEL CYCLE Vacuum Pumping Water Detritiation System: characterisation of LPCE Catalyst Packing mixture, electrolysers & combined WDS-ISS operation Isotopic Separation System: 16

17 ITER SYSTEMS HEATING Plasma heating & fuelling systems: - Ohmnic heating - Neutral beam injectors - Electron Cyclotron radiofrequency - Ion Cyclotron radiofrequency - Pellet Injection - Gas puffing SPIDER Source for Production of Ion of Deuterium MITICA Megavolt ITER Injector & Concept Advancement 17

18 ITER SYSTEMS HEATING ELECTRON CYCLOTRON 4x2MW 8x1MW 18

19 ITER SYSTEMS DIAGNOSTICS Measurement systems for the ITER plasma and first wall Provide essential information to: protect the machine from damage allow the plasma to be controlled study the plasma Front-end hardware mounted on/in the vacuum vessel, divertor cassettes, port plugs and ports Large systems, extending from the plasma to the control room Include both hardware and software 19

20 ITER SYSTEMS DIAGNOSTICS 13 diagnostic systems: and: Tokamak services (cables, conduits, connectors etc.) 3 upper port plugs, 2 equatorial port plugs Port structures (shielding modules, support structures) Diagnostic integration Diagnostic supply by ITER Partner Magnetics diagnostics Inner-divertor target thermocouples Plasma position reflectometer Core-plasma charge-exchange recombination spectroscopy Radial neutron camera + gamma spectrometer (enabling) Equatorial visible/ir wide angle viewing system High resolution neutron spectrometer (enabling) H-phase hard X-ray detector Core-plasma LIDAR Thomson scattering Collective Thomson scattering front end enabling Bolometers Pressure gauges 20

21 ITER SYSTEMS DIAGNOSTIC TECHNOLOGIES Sensors Fast, large area, high sensitivity, broadband (near UV to near IR) detectors High framing rate, 2D CCD cameras in visible and IR Miniaturized metal thermo-resistors Precision-wound coils using in-vessel compatible conductors D-D and D-T Neutron detectors o Diamond or organic neutron scintillators coupled to photomultipliers o Fission chambers o Gas electron multipliers Calibration sources Compact fixed and movable neutron (2.5 MeV and 14 MeV), gamma and alpha sources Pt or Au thin films resistors on thin film ceramic or Mica substrates Rogowski coils Cabling & connectors Up to 80 km of vacuum compatible, radiation tolerant cables Numerous conventional and bespoke connectors Radiation tolerant vacuum feedthroughs Low temperature co-fired coils 21

22 ITER SYSTEMS TBS ITER should test Tritium Breeding Module (TBM) concepts that would lead in a future reactor to tritium self-sufficiency and to the extraction of high grade heat and electricity production. Structural material HCPB He-Cooled Pebble-Bed EUROFER HCLL He-Cooled Lithium-Lead Coolant Helium, 8 MPa, 300 / 500 C Tritium breeder, neutron multiplier Solid Li 2 TiO 3 / Li 4 SiO 4, Be Liquid Pb-15.7Li Plasma Rear Forschungszentrum Karlsruhe 22

23 ITER SYSTEMS SYSTEMS INTEGRATION Configuration management and other issues Configuration Control Project Change Control Design Review Design Integration Site Assembly / DWS creation Testing/Commissioning Plan Integrated CAD Design & Support 23

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