of 18 slides

1
European contribution to the Design and RD
activities in view of the start of the ITER
construction phase

• Maurizio Gasparotto on behalf of the EFDA Team

2
Outline

• Introduction
• General remarks on the EU contribution to ITER
  design and RD
• A view on some of the EU supported activities in
  preparation for ITER component procurement
• Conclusions

3
EU Contribution to ITER design and RD

• Main objectives
• continuing, and in some areas expanding, the
  effort in areas where design and RD are still
  required
• continuing and completing manufacturing RD to
  determine the most technically and cost effective
  manufacturing methods
• preparing new test facilities
• supporting the European site preparation process
  and the preparation of safety and licensing
  documentation
• maintaining support to EU industries

4
ITER Vacuum Vessel
Fabrication routeheavy jigs welded to the VV
inner wall to limit the shrinkage
Full size mock-up (poloidal sector) weight 20
tons

• Additional activities
• Development of FE global/local model for
  prediction of weld distortion
• Alternative fabrication methode-beam welding
  without using jigs, better control of shrinkages

5
ITER First Wall Panels

• Be tiles 10 mm thick bonded to CuCrZr alloy
• Hot Isostatic Pressing mock-ups successfully
  tested at 0.6 MW/m2 30000 cycles (acceptance
  criteria detachment of Be tiles at 3 MW/m2)
• Fast Induction Brazing (to retain CuCrZr
  mechanical properties) alternative technique
  potentially cheaper
• A silver free braze alloy is under development

Induction brazing equipment for brazing scale-one
FW panel prototype
Inductor for brazing FW mock-ups
6
ITER Shield Blocks

• Conventional fabrication technique machining and
  welding processes (drawbacks expensive, risk of
  water leakages due to large number of welds)
• Alternative fabrication route based on HIPping
  (drawback deformation due to shrinkage of the
  powder during solidification)
• New design two regions
• Forged SS block on the front region
• SS powder with embedded cooling tubes in the rear
  region
• Advantage No seal welds are exposed to the
  vacuum design flexibility

NBI port region of the Blanket
7
ITER Divertor

• CuCrZr cooling tube with CFC or W blocks joined
  by welds
• HIPping technique
• CFC successfully tested (1000 cycles at 20 MW/m2
  1000 cycles at 23 MW/m2). W successfully
  tested (1000 cycles at 10 MW/m2).
• Alternative technique Hot Radial Pressing
• Full scale Divertor components qualification of
  manufaturing process and assembly procedure
• Remote Handling qualification in the Divertor
  Refurbishment Platform (Brasimone, Italy)

8
ITER TF - PF Conductor
PF Conductor Insert

• Advanced strand
• minimum non-copper critical current density
  800 A/mm2 at 12 T and 4.2 K. Target value Jc
  1100 A/mm2
• Four TFMC type conductors produced with advanced
  strands show degradation in the performance
  larger than expected. A programme to improve the
  conductor performance was launched

9
Remote Handling
Divertor Test Platform 2 (Tampere, Finland)

• Two stages approach
• Radial movement of cassettes along the divertor
  level RH ducts using the Cassette Multifunctional
  Mover
• Transfer of cassettes from locations at same
  toroidal distance from RH ports using the
  Cassette Toroidal Mover

10
Physics Integration
ELM experiments have now been concluded (0.5 -
1.0 - 1.5 MJ/m2, Dt 500 ms) QSPA Facility in
TRINITI (RF)
CFC target after 100 1.5 MJ/m2 ELMs
W target after 100 1.5 MJ/m2 ELMs
11
ITER Diagnostics

• About 45 types of diagnostics in ITER (9
  developed in EU)
• Development of radiation-hard components
• Effort in EU also supporting Design and
  Integration of Diagnostics Port Plugs

Divertor halo-current Rogowski coils
Silicon-nitride Brewster-angle window assembly
Plug displacement for disruptions
12
Electron Cyclotron (EC) Upper Launcher
170 GHz
180 GHz
160 GHz
190 GHz
150 GHz
UL

• 170 GHz compromise solution for common set of
  sources
• Equatorial (flt170 GHz preferred) for core plasma
  heating 1 launcher
• Upper (fgt170 GHz preferred) for MHD mode
  stabilization4 launchers

EL
13
EC Gyrotrons
Full power, steady state testing of the 2 MW, 170
GHz, gyrotron
EC Test Facility established at CRPP, Lausanne
(CH)
14
Ion Cyclotron (IC) Antenna

• Detailed designs of internal and external
  matching concepts for ICRF antenna are being
  integrated into the ITER environment

Overview of internal matching design for antenna
External matching design side section of the
port plug
15
Neutral Beam System

• Ion Beam source
• W filaments
• Radio frequency
• Accelerator
• SINGAP (EU)
• MAMUG (JAPAN)

• Electron and ion current for 600 s beam pulse
  current density 250 A/m² in D. Small scale source
  at IPP Garching
• Full scale RD test facility is planned to be
  built at RFX-Padua (Italy)

16
Test Blanket Module
TBM cooling plate mock-up ready for testing
Cooling Plate Mock-up ready for testing

• Next step
• Thermo-mechanical testing in DIADEMO PbLi /
  Helium cooling loop (CEA - France)

17
ITER Site Preparation

• Licensing Specifications and Tendering for the
  contract for final writing of the Preliminary
  Safety Report completed
• ITER Site Clearing Technical input for the
  specifications for ITER site clearing available.
  Area to be cleared in different stages about 100
  h
• ITER site excavations Study on ITER site layout
  optimization with respect to volumes and costs of
  excavations available
• Potable water supply and effluent release
  contract placed for potable water supply and
  effluent release

• Temporary Power Supply to ITER Site The contract
  for the procurement of a 5 km cable to reinforce
  the line Cadarache (63 kV station) to Tore Supra
  was launched
• Qualification of Seismic Isolators
• On Site PF Fabrication Study

18
Conclusions

• EUROPE, as a major contributor to ITER, has
  strongly supported the project in various areas
• A strong effort will continue to be made by the
  EU fusion Associations and Industries to support
  the ITER program
• Manufacturing RD is carried out to determine the
  most technically and cost effective manufacturing
  methods
• A number of facilities to develop and test
  mock/ups and components are in preparation
• Additional RD is still needed in some areas
  (Diagnostics, HCD, RH, TBM)
• We are convinced that the fusion community is now
  ready
• to finalise the technical specifications needed
  for the procurement for most of the ITER
  components
• and therefore to start the construction phase as
  soon as
• a) the legal entities will be established
• b) few open issues are clarified