Materials

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Materials Manufacturing Technologies
requirement for Cryostat Vacuum Vessel In-wall
shield System of ITER
Bharat Doshi Project Manager (ITER-India)
Institute for Plasma Research,Gandhinagar,India
23rd July 2008
WSFT-IPR-Gandhinagar.
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Out line of the Presentation

• Introduction to ITER ITER Systems

• Cryostat In-wall Shield System description

• Material requirements for Vacuum Vessel In-wall
  shield system
• Cryostat System

• Manufacturing Technologies needed for Cryostat
  System
• Vacuum Vessel In-wall shield system

• Summary

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INTERNATIONAL THERMO-NUCLEAR EXPERIMENTAL REACTOR
(ITER)
ITER is one of its kind, and it will be the
first biggest nuclear fusion facility to be
licensed in cadarache, France.

• Major systems includes..
• Super conducting Magnets (CS,PF TF)
• Vacuum Vessel (plasma chamber)
• First wall (Blanket modules, Divertor
  cassettes,Limiters etc.)
• Cryostat,VVPSS Thermal shields
• Vacuum Pumping systems
• Heating current drive systems
• Diagnostics
• Cryoplant Cryodistribution
• Cooling water system
• Tritium plant
• Power supplies
• CODAC

Fusion Power 500 MW Plasma Volume 840
m3 Nominal Plasma Current 15 MA Typical Density
1020 m-3
ITER construction is multidimensional,
multicultural and spread across many time zones
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INDIAN CONTRIBUTION (9- PROCUREMENT PACKAGES)
Diagnostic Neutral Beam (WBS 5.3.7) RF sources
monitoring and control for IC HCD (WBS
5.1.3) Gyrotrons for plasma start up(WBS
Power supplies for DNB, RF, Gyrotrons (WBS
5.1.4, 5.2.4, 5.5)
Cryostat WBS 2.4
Diagnostics (3.5) WBS 5.5
Industrial Projects
Vacuum vessel in wall shields WBS 1.5
Cryo distribution cryo line system (WBS 3.4)
ITER heat rejection, component cooling and
chilled water system WBS 2.6
R D Projects
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ITER Cryostat System
Cryostat
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Cryostat System Functions

• Cryostat shall form a vacuum tight container,
  surrounding the entire Tokamak Basic Machine. It
  shall provide the vacuum for the super-conducting
  magnets, and shall form part of the secondary
  confinement barrier for radioactive inventory
  inside VV. The cryostat shall include
  overpressure protection for itself.
• Cryostat allows passive removal of decay heat,
  from VV In vessel components.
• Cryostat has penetrations for magnet feeders,
  water cooling pipes, instrumentation
  feed-through, cryostat pumping systems etc.
• Cryostat has penetrations for access to the VV
  ports (45 ports).
• Cryostat has penetrations for access, for
  maintenance equipment, into the cryostat.
• Cryostat has penetrations for access to the CS
  PF coil, for possible removal.
• Cryostat shall transfer all the loads that derive
  from the tokamak basic machine, from the
  cryostat itself, to the floor of the tokamak pit
  through its support structures (during the normal
  off-normal operational regimes, and at
  specified accidental conditions).

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Cryostat System configuration

• Cryostat is a cylindrical pressure vessel, with
  its axis vertical, and with a flat bottom and a
  tori-spherical top.
• The maximum diameter of the outer cylindrical
  part shall be 29 m.
• The diameter of outer cylindrical part shall
  reduce to 19 m below the VV divertor ports.
• These two cylinders of different diameters shall
  be connected to a horizontal ring, which shall be
  the platform to cater for the TF magnets and the
  vacuum vessel.
• The horizontal ring shall be supported by 18
  pillars installed on the pit floor.
• The port penetrations shall be connected to VV
  port ducts and bioshield port cells by metallic
  bellows to compensate all relative movements.
• Cryostat bottom end shall be just above the pit
  floor level.
• Cryostat shall be connected to vacuum pumps and
  the vacuum monitoring system.

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Design Performance Requirements
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Cryostat Performance Requirements
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Deliverables

• One Full Cryostat
• Factory fabrication ITER Site
• fabrication
• Tokamak hall installation
• Top dome shaped upper head
• Upper Cylinder
• Lower Cylinder
• Base Section
• Cryostat penetrations
• Cryostat support structure
• Gravity support columns
• Cryostat venting overpressure
• protection system

580.495 MT
616.037 MT
654.002 MT
1384.347 MT
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Factory Fabrication
      Length 4320 mm       Width 1350
mm       Height 1350 mm Material SS304 Qty.
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Site Fabrication
Lower Cylinder Assembly
Upper Cylinder Assembly
Base Section Assembly
Top Lid Assembly
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Site Assembly in ITER hall
Each assembly being moved in ITER hall
Field weld Joint in ITER hall NDT ( 300 m)
ITER Tokamak building With Cryostat Assembled
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RD in Welding Technology
3A. Hybrid Welded 316 LN 20 mm thick plate
1. NG-TIG weld in 40
mm thick SS316L plate
Hybrid Set-up
Hybrid Configuration
3B. 316 LN Tube Hybrid welded
4A. RPEB weld in 60 mm thick 316L
2B. Laser weld 20 mm AISI 304L plate
4B. RPEB welds
2A. Laser weld 60 mm SS in 13 passes
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WELDING REQUIREMENTS

• Total length of full penetration weld joints of
  60 mm thick plate for site assembly 350 m
• Total weight of deposited metal during site
  assembly 1200 Kg.
• Many welding machines to operate in
  synchronization for these joints
• Total length of full penetration weld joints of
  60 mm for sub-assemblies 700 m (approx.)
• Total weight of deposited metal for
  sub-assemblies 2100 Kg.
• Requirement for welding automation (TIG, MIG,
  SMAW)
• Various new welding technology like RPEBW, NGTIG
  needs to be developed.

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ITER VV-IWS BLOCKS

• To stop energetic neutron within vessel boundary
  and to reduce TF ripple.
• ITER vacuum vessel is double wall construction.
  Space between outer shell and inner shell is
  used for placing VV-IWS Blocks.

Typical in-board VV-IWS Block
Out-board VV-IWS Blocks assembled
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ITER VV-IWS BLOCKS ASSEMBLY
Shield block assembly
ITER VV SECTOR
ITER VV ASSEMBLY
VV In-wall shield segmentation
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Material Requirements

• 6000 blocks for VS and VS joints. Total weight
  of fabricated blocks is approximately 1777 t.
• Following different materials are required for
  VV-IWS blocks
• SS 304B4 (40 mm thick plates) 1735 t
• SS304B7 (40 mm thick plates) 0134 t
• SS430 (40 mm thick plates) 350 t
• SS 316 L(N)(IG2) (40-60 mm thick plates) 100 t
• XM-19 (30 50 mm diameter round bars) 50 t

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SS304 B4

• 304B4 type, Grade B austenitic stainless steel
  plates for neutron shielding inserts in the
  inboard region in the ITER
• Vacuum Vessel, conform to ASTM A 887-89
  (2004).

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SS304 B7

• 304B7 type, Grade B austenitic stainless steel
  plates for neutron shielding inserts in the
  inboard region in the ITER
• Vacuum Vessel, conform to ASTM A 887-89
  (2004).

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SS316LN (IG2)
Unspecified elements contents as low as possible
and not exceeding trace element level. Ta Nb
Ti 0.15
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SS430
Chromium stainless steel plate type 430 (UNS
S43000) for ferromagnetic inserts for the ITER
Vacuum Vessel.
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Summary

Material required for Vacuum Vessel In-wall
Shield System Cryostat of ITER
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Summary

• Manufacturing Technologies required to be
  developed for Cryostat Vacuum Vessel In-wall
  Shield System of ITER
• Advanced Cutting
• Plasma
• YAG Laser
• Water jet
• Welding Technology
• NGTIG (Hot wire NGTIG)
• MAG
• RPEB
• YAG LASER
• (Wire-fill Laser without shielding gas/with
  shielding gas)
• Laser-MIG Hybrid
• NDT technology (RESTRICTED ACCESS)
• UT(Augur, Phased Array, TOFD)
• RT
• PT

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Thank you for your attention
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