ITER Towards the Construction Y. Shimomura for the ITER International and Participant Teams 23rd Symposium on Fusion Technology Venice, 20-24th September, 2004 Content Technical Preparations for Construction Design Improvements Manufacturing R&D Procurement Specification Writing
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for the ITER International and Participant Teams
23rd Symposium on Fusion Technology
Venice, 20-24th September, 2004
International TeamTask Agreement EU Team Regulator
JA Team Regulator
Blanket Working Group RF Team
Diagnostic Working Group China Team
International Tokamak Physics Activities US Team
S. Korea Team
Nb3Sn, 6 modules
Poloidal Field Coil
24 m high x 28 m dia.
Toroidal Field Coil
Nb3Sn, 18, wedged
Port Plug (IC Heating)
3 test blankets
Fusion Power: 500 MW
Plasma Volume: 840 m3
Nominal Plasma Current: 15 MA
Typical Temperature: 20 keV
Typical Density: 1020 m-3
(Problem of one-sided
and limited access)
Ultrasound of 60 mm plate
Photothermal Camera Technique
Vacuum vessel weld inspection
LICENSE TO CONSTRUCT
TOKAMAK ASSEMBLY STARTS
Task Forces established with PT/IT membership to complete work
in necessary detail and with industrial realism
(Trial production and test)
ITER needs “virtual product data management” (VPDM) software for 3D digital mockup, essential for configuration management.
clash detection, utility routing, collaborative design with the Participants, need better tools to control the configuration and allocation of the available space.
CATIA 4 soon obsolete. Should upgrade to CATIA 5:
nearly all procurement models are in one system;
be in tune with manufacturers, who have already upgraded, and rehearse conversion processes with other manufacturer’s CAD systems;
tailor software systems essential in construction;
All project legacy data in CATIA, so no need to transfer to alternative if the project can obtain a good deal on price.
Project anyway has to work out means to deal with other CAD systems, to an extent depending on the level of integration of the system with others, as well as the detail level of the procurement.
During late 2003 and 2004 ITER IT has implemented Enovia VPM as data manager in conjunction with CATIA V4 and V5.
Process well-advanced with a complete switch to production work in CATIA V5 planned for the end of 2004.
* Friday, A. Costley, “Technological Challenges of ITER Diagnostics”
(1)EC H&CD uses 3 upper ports for the power upgrade
100Progress of R&D in NBI - MeV negative ion NB
High-Current Density negative ion beam with 1 MeV successfully produced.
current density (H-)
(achieved) 1), 2)
20.4 A (H-)
17.4 A (D-)
Note 1) Power supply is limited to max. 1 A.
2) Heat removal of beam dump was limited to
100A/m2 . After the modification, try to
produce the required beam (200 A/ m2 ).
ECRF: Status of Gyrotron Development
Progress of Gyrotron R&D
Test of 170 GHz/1 MW in CW operation (> 400 sec) is in progress.
Efficient Use of ITER
Involvement of Worldwide Community
ITER Remote Experimental Site
Exp. Center 1
Exp. Center 2
Example: 3 shift/day on site (night shift for monitoring and support of remote experiment)
1 or 2 shift(s)/day on remote experimental sites
Base programme: 2 shift/day operation/experiment on-site
Cadarache or Rokkasho
(professionals + support staff)
Staff of DG
• Project Management
• Computer Network
• Technical work
• Clerical work
for construction phase
Host provides Buildings and Utilities. Remaining allocation (Flex.) depends on site.