Divertor and Blanket Systems: Design, Required technologies and Schedule M. Merola Head of the Internal Components Division. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization . ITER Internal Components.
Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author.While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server.
Divertor and Blanket Systems:
Design, Required technologies and Schedule
Head of the Internal Components Division
The views and opinions expressed herein do not necessarily reflect those of the ITER Organization.
ITER Internal Components
Overview of Material Mass
Divertor Cassette Layout
in a circular array held in position by two concentric radial rails .
Status of Divertor
of Plasma Facing Units
Divertor Qualification Prototypes
All 3 Domestic Agencies have been qualified.
Status of W Technology R&D in EU
2000 cycles at 15 MW/m2 on W
Unirradiated- 1000 cycles x 20 MW/m2 – no failure
200°C, 0.1 and 0.5 dpa in tungsten
- Successfully tested up to 18 MW/m2
Most of all the W repaired monoblocks behaved like not-repaired ones
Blanket System Functions
Shield Block (semi-permanent)
FW Panel (separable)
~850 – 1240 mm
~1240 – 2000 mm
Design Heat load on blanket
First Wall Finger Design
Normal Heat Flux Finger:
•q’’ = ~ 1-2 MW/m2
•Steel Cooling Pipes
Enhanced Heat Flux Finger:
•q’’ < ~ 5 MW/m2
•Explosion bonding (SS/CuCrZr) + brazing (Be/CuCrZr)
SS Back Plate
FW Pre-Qualification Requirements
2 slopes, 4 facets
6 Fingers in 1 to 1 scale
I. Demonstration/validation joining of Be/CuCrZr and SS/CuCrZrjoint (done)
II. Semi-prototype production/validation of large scale components (on-going)
Shield Block Design
General Tolerances described in Standards do NOT always meet our requirements
ISO 2768-1:1989 Tolerances for linear and angular dimensions …
ISO 2768-2:1989 Geometrical tolerances ...
Welded structures made of austenitic steels:
NG-TIG, EB, Laser, TIG, MIG, …
High heat flux joining technologies (Tungsten, Beryllium, CuCrZr):
HIP’ing, brazing, casting, EB
Heat Flux Testing of actively cooled components
RX, UT, …
Piping, flexible supports for pipes
Insulating coatings, Low friction coatings, Anti-size coatings
Precise machining, metrology
High-Vacuum technologies, Pressure Tests, He Leak Tests
Manufacturing / Welding Qualifications
NDT of welds in Steel Supports
N.B. ITER Vacuum Handbook requirement: use of qualified liquid penetrants
Engineering Support Services
Design supporting analysis (Electro-Magnetic, thermal, mechanical)
Development of component design, including the production of 2D drawings and 3D models.
This activity requires the possibility to receive and deliver CAD files in of CATIA_V5 format.
Good knowledge and understanding of the codes, standards, and design criteria used in ITER.
The work may require the presence of the Contractor’s personnel at the working site of the ITER Organization, for extended periods of time, for the purpose of design review and data gathering.
Divertor Procurement Schedule
• 17.P2C.RF Divertor Dome: signed 9th June 2009
• 17.P2A.JA Divertor Outer Target: signed 17th June 2009
• 17.P2D.RF Divertor Heat Flux Tests: signed 23rd February 2010
• 17.P2B.EU Divertor Inner Target: signed 22nd March 2010
• 17.P1.EU Divertor Cassette and Integration: signed 8th May 2012
• 17.P2E.EU Divertor Rails: September 2014
Blanket Procurement Schedule
• 16.P1A.CN/EU/RF Blanket First Wall: November 2013
• 16.P1B.CN/KO Blanket Shield Block: November 2013
• 16.P3.RF Blanket Module Connections: July 2014
• 15.P1A.EU Blanket Manifolds: March 2014
Summary and Conclusions