Presentation is loading. Please wait.

Presentation is loading. Please wait.

W coating of CFC tiles for the JET new wall - Task Agreement: JW6-TA-EP2-ILC-05 Manufacturing and testing of W-coated CFC tiles for installation in JET.

Published byJodie Norton Modified over 9 years ago

Similar presentations

Presentation on theme: "W coating of CFC tiles for the JET new wall - Task Agreement: JW6-TA-EP2-ILC-05 Manufacturing and testing of W-coated CFC tiles for installation in JET."— Presentation transcript:

1 W coating of CFC tiles for the JET new wall - Task Agreement: JW6-TA-EP2-ILC-05 Manufacturing and testing of W-coated CFC tiles for installation in JET for the ITER-like Wall project - Task Agreement: JW8-FT-JET-A Tungsten erosion in the JET divertor Cristian Ruset, Eduard Grigore EURATOM-MEdC Association NATIONAL INSTITUTE FOR LASER, PLASMA AND RADIATION PHYSICS, BUCHAREST, ROMANIA NATIONAL INSTITUTE FOR LASER, PLASMA AND RADIATION PHYSICS, BUCHAREST, ROMANIA NILPRP EURATOM MEdC Association days, Bucharest 26-27 November 2009

2 OUTLINE Overview of the Task Agreement: JW6-TA-EP2-ILC-05 “Manufacturing and testing of W-coated CFC tiles for installation in JET for the ITER-like Wall project” Current status Future actions Conclusions EURATOM MEdC Association days, Bucharest 26-27 November 2009

3 The material selection for the ITER ( in particular for the first wall) has a capital importance on the overall performance of the fusion reactor. Requirements: - Good mechanical properties, very good resistance to cyclic high thermal load, low sputtering yield, low tritium retention, low activation under neutron irradiation and so on.. Candidates: - C (CFC- Carbon fiber composite): disadvantage high tritium retention - Be: disadvantage low melting point (1555 K) - W: seems to be a good candidate EURATOM MEdC Association days, Bucharest 26-27 November 2009

4 In the R&D phase of the ITER-like Wall (ILW) project (2005-2006) it was demonstrated that W coatings deposited on CFC by Combined Magnetron Sputtering and Ion Implantation (CMSII) technology, which was developed in MEdC Association, had a better thermo-mechanical properties compared with other coating technologies. The first option for ITER is a compromise meaning full beryllium main wall with CFC at the strike points and tungsten divertor baffles and dome. In order to test this combination including Be, W and W coated CFC tiles, the ITER like Wall project has been launched at JET (Joint European Torus) Requirements for the W coatings: Thickness 10-15μm Thickness 10-15μm Impurity content at 5 μm: C less that 10 at.%, O less than 5 at. % Impurity content at 5 μm: C less that 10 at.%, O less than 5 at. % Cyclic high flux heat resistance: 200 pulses at a power density of 10.5 MW/m 2 for 5 s and Thermal screening 26 pulses with power densities from 6.0 MW/m 2 to 23.5 MW/m 2 and duration from 10 s to 1 s (Tests performed at Ion beam test facility IPP Garching) Cyclic high flux heat resistance: 200 pulses at a power density of 10.5 MW/m 2 for 5 s and Thermal screening 26 pulses with power densities from 6.0 MW/m 2 to 23.5 MW/m 2 and duration from 10 s to 1 s (Tests performed at Ion beam test facility IPP Garching) EURATOM MEdC Association days, Bucharest 26-27 November 2009

5 W Mo SEM image of a W/Mo coatingGDOES depth profile for a W/Mo coating Structure and chemical composition of the W coatings EURATOM MEdC Association days, Bucharest 26-27 November 2009

6 SEM surface images of the coating deposited by CMSII (a) and by conventional magnetron sputtering (b) after cyclic thermal loading (200 pulses of 10.5 MW/m 2 / 5 s) Cyclic thermal loading test of the coated CFC tiles EURATOM MEdC Association days, Bucharest 26-27 November 2009

7 Image of the deposition equipment Deposition equipment EURATOM MEdC Association days, Bucharest 26-27 November 2009

8 Interior view of the JET tokamak Technical specification of the CFC coated tiles: - Main chamber 10-15μm W coating - Divertor 200 μm W coating After testing some prototype tiles coated with 20 μm W by CMSII, a decision concerning the coating of ~800 divertor tiles by using CMSII has been made. The task agreement JW6-TA-EP2-ILC-05 was extended. EURATOM MEdC Association days, Bucharest 26-27 November 2009

9 Tiles – C from the main chamber coating thickness 10-15  m Diagnostic covers and shinethrough protection tiles from the main chamber coating thickness 10-15  m

10 G 4 divertor tiles coated with 10-15  m W in series production G 6 and G7 divertor tiles coated with 20-25  m W in series production EURATOM MEdC Association days, Bucharest 26-27 November 2009

11 Current status of the W coating production for the JET tiles at 20.11.2009 Status of coating divertor tiles Divertor G3 tiles – 49 tiles (100%) Divertor G3 tiles – 49 tiles (100%) Divertor G4 tiles – 103 tiles (100%) Divertor G4 tiles – 103 tiles (100%) Divertor HFGC tiles – 102 tiles (100%) Divertor HFGC tiles – 102 tiles (100%) Divertor G6-102 tiles (100%) Divertor G6-102 tiles (100%) Divertor G7-52 tiles 20 µm(97%) Divertor G7-52 tiles 20 µm (97%) Divertor Mushroom tiles - 6 tiles (Ready to be delivered to JET) (100%) Divertor Mushroom tiles - 6 tiles (Ready to be delivered to JET) (100%) Divertor G1 - 106 tiles 20 µm (Ready to be delivered to JET) (100%) Divertor G1 - 106 tiles 20 µm (Ready to be delivered to JET) (100%) Divertor G8 -105 tiles 20 µm(Ready to be delivered to JET) (100%) Divertor G8 -105 tiles 20 µm (Ready to be delivered to JET) (100%) LBSRP 4 of 106 tiles 20 µm(4%) LBSRP 4 of 106 tiles 20 µm (4%) Total divertor coated tiles 629 (85%) EURATOM MEdC Association days, Bucharest 26-27 November 2009

12 Status of coating main chamber tiles Inner Wall Cladding – 70 tiles (100%) Inner Wall Cladding – 70 tiles (100%) Shinethrough Protection – 54 tiles (51%) Shinethrough Protection – 54 tiles (51%) Restrained Ring Protection – 57 tiles (100%) Restrained Ring Protection – 57 tiles (100%) LBSRP Protection – 93 tiles (100%) LBSRP Protection – 93 tiles (100%) IWGL (Be) – 68 tiles (100%) IWGL (Be) – 68 tiles (100%) Diagnostic covers – 64 tiles (79%) Diagnostic covers – 64 tiles (79%) Divertor B tiles – 80 tiles (95%) (Ready to be delivered to JET) Divertor B tiles – 80 tiles (95%) (Ready to be delivered to JET) Divertor C tiles-104 tiles (100%) (Ready to be delivered to JET) Divertor C tiles-104 tiles (100%) (Ready to be delivered to JET) Saddle coil 2 tiles ( 11%) Saddle coil 2 tiles ( 11%) Poloidal limiters ( 9 tiles; uncoated) Poloidal limiters ( 9 tiles; uncoated) Total main chamber coated tiles 572 All prototypes and ~ 12% of tiles have passed the HHFT (High Heat Flux Tests) performed at IPP Garching EURATOM MEdC Association days, Bucharest 26-27 November 2009

13 According to ITER Like Wall Project Management plan (JW6-PM-EP2-ILC- 05) (Annex 1) milestones for the year 2009: Delivery to JET of 25% of the 10 µm main chamber tiles and 25% of the divertor W-coated CFC tiles. Status: Done Due date: 30.06.09. Status: Done Production coating of the second batch comprising 50% of the divertor tiles Production coating of the second batch comprising 50% of the divertor tiles Status: Done Due date: 31.12.09. Status: Done Production coating of all the remaining tiles Due date: 30.09.10 Final report and outstanding documentation Final report and outstanding documentation Due date: 14.12.10 Future actions: EURATOM MEdC Association days, Bucharest 26-27 November 2009

14 Marker tiles for erosion measurements ( Tungsten erosion in the JET divertor TA JW8-FT-JET-A) A number of markers (a multilayered structure W/Mo/W/Mo) will be used for measurements of wall erosion Tiles type used as markers: G1, G8, G6, G7 (4 each type) Required coating structure: Mo (first layer): 2-3 µm; W (first layer): 12-14 µm; Mo (second layer); 3-4 µm; W (second layer): 3-4 µm The markers were already coated and sent to IPP Garching EURATOM MEdC Association days, Bucharest 26-27 November 2009

15 GDOES depth profile for a W/Mo coatingSEM image for a W/Mo structure EURATOM MEdC Association days, Bucharest 26-27 November 2009

16 CONCLUSIONS Up now ~ 85% (629 tiles) of the divertor have been coated. 408 tiles have been sent already to JET and 221 are ready to be delivered. 274 tiles from main chamber have been delivered to JET, and 318 are ready to be delivery. Results of the HHF test at IPP - tested tiles: 117 (~ 12% of series production) - tested tiles: 117 (~ 12% of series production) - tiles which passed the tests: 117 - tiles which passed the tests: 117 - rejected tiles: 0 - rejected tiles: 0 The works are in schedule

17 Thank you for your attention!

Download ppt "W coating of CFC tiles for the JET new wall - Task Agreement: JW6-TA-EP2-ILC-05 Manufacturing and testing of W-coated CFC tiles for installation in JET."

Similar presentations

Report IPP Garching EU Task Force PWI Meeting, Cadarache Oct 17-19 2005 1 Max-Planck-Institut für Plasmaphysik compiled by Arne Kallenbach (IPP - EU-PWI.

Report IPP Garching EU Task Force PWI Meeting, Cadarache Oct Max-Planck-Institut für Plasmaphysik compiled by Arne Kallenbach (IPP - EU-PWI.
1E. TsitronePWI TF meeting 13-15/11/2006 Euratom ITER divertor status Annual ITER divertor meeting (4-6 october 2006, St Petersbourg) Memorandum of undestanding.

1E. TsitronePWI TF meeting 13-15/11/2006 Euratom ITER divertor status Annual ITER divertor meeting (4-6 october 2006, St Petersbourg) Memorandum of undestanding.
EU-PWI-Task Force V. Philipps, TF Meeting, 17-19 2005 Cadarache Status of ITER like wall project V. Philipps ITER 2 options are under preparation, decision.

EU-PWI-Task Force V. Philipps, TF Meeting, Cadarache Status of ITER like wall project V. Philipps ITER 2 options are under preparation, decision.
A new look at the specification of ITER plasma wall interaction and tritium retention J. Roth a, J. Davis c, R. Doerner d, A. Haasz c, A. Kallenbach a,

A new look at the specification of ITER plasma wall interaction and tritium retention J. Roth a, J. Davis c, R. Doerner d, A. Haasz c, A. Kallenbach a,
JET PFC Analysis, TFFT and the ILW

JET PFC Analysis, TFFT and the ILW
WP10-PWI-01-02-01(02)/TEKES/BS(PS) Characterization of retention mechanisms in AUG Monitoring meeting of the EFDA PWI SEWG on Gas Balance and Fuel Retention,

WP10-PWI (02)/TEKES/BS(PS) Characterization of retention mechanisms in AUG Monitoring meeting of the EFDA PWI SEWG on Gas Balance and Fuel Retention,
Kazuyoshi Sugiyama, SEWG meeting, Culham, 9 -10 July 2007 1 Outline: 1.Introduction 2.Experimental procedure 3.Result 4.Summary Kazuyoshi Sugiyama First.

Kazuyoshi Sugiyama, SEWG meeting, Culham, July Outline: 1.Introduction 2.Experimental procedure 3.Result 4.Summary Kazuyoshi Sugiyama First.
Kazuyoshi Sugiyama, SEWG meeting on Fuel retention, Garching, July 20 2010 1 Contribution of Boron on the D retention in the AUG full-W wall regime Max-Planck-Institut.

Kazuyoshi Sugiyama, SEWG meeting on Fuel retention, Garching, July Contribution of Boron on the D retention in the AUG full-W wall regime Max-Planck-Institut.
C. Björkas, K. Vörtler and K. Nordlund Department of Physics, University of Helsinki Joint TFE-SEWG - Material Migration and Material Mixing meeting MD.

C. Björkas, K. Vörtler and K. Nordlund Department of Physics, University of Helsinki Joint TFE-SEWG - Material Migration and Material Mixing meeting MD.
EU PWI Task Force V. Philipps, SEWG mixed materials, 21.6.06 JET ITER-like Wall Project : Material choice, issues to investigate and role of new SEWG ITER-like.

EU PWI Task Force V. Philipps, SEWG mixed materials, JET ITER-like Wall Project : Material choice, issues to investigate and role of new SEWG ITER-like.
1. Qualifying carbon as PFC Erosion (see report S. Brezinsek ) along plasma wetted areas, effect of substrate Local C migration to gaps Fuel retention.

1. Qualifying carbon as PFC Erosion (see report S. Brezinsek ) along plasma wetted areas, effect of substrate Local C migration to gaps Fuel retention.
Mixed materials in JET 2006 J P Coad Present JET situation Deposited films at the inner divertor (plasma-facing surfaces) Films deposited in shadowed areas.

Mixed materials in JET 2006 J P Coad Present JET situation Deposited films at the inner divertor (plasma-facing surfaces) Films deposited in shadowed areas.
PWI questions of ITER review working groups WG1 and WG8 : Materials Introduction EU PWI TF V. Philipps, EU PWI TF meeting, Oct 2007, Madrid V. Philipps,

PWI questions of ITER review working groups WG1 and WG8 : Materials Introduction EU PWI TF V. Philipps, EU PWI TF meeting, Oct 2007, Madrid V. Philipps,
J. Roth Bilateral Agreements EU-DOE: e.g.: PISCES operation (following talk by Russ Doerner) Bilateral Agreement EU-Russia: collaboration on Material damage.

J. Roth Bilateral Agreements EU-DOE: e.g.: PISCES operation (following talk by Russ Doerner) Bilateral Agreement EU-Russia: collaboration on Material damage.
P. Coad, J. Likonen, H. Bergsåker, M. Rubel, I. Uytdenhouwen, A. Widdowson JET mixed Be/C/O layers SEWG meeting on mixed materials, 9.-10.7.2007, JET.

P. Coad, J. Likonen, H. Bergsåker, M. Rubel, I. Uytdenhouwen, A. Widdowson JET mixed Be/C/O layers SEWG meeting on mixed materials, , JET.
No 1 V. Philipps, SEWG Fuel retention, July 2010, Garching Joint TEXTOR, MAGNUM and PISCES experiments on retention in W and mixed W/C system V. Philipps,

No 1 V. Philipps, SEWG Fuel retention, July 2010, Garching Joint TEXTOR, MAGNUM and PISCES experiments on retention in W and mixed W/C system V. Philipps,
Institute for Plasma Physics Rijnhuizen D retention in W and mixed systems in Pilot-PSI G. De Temmerman a, K. Bystrov a, L. Marot b, M. Mayer c, J.J. Zielinski.

Institute for Plasma Physics Rijnhuizen D retention in W and mixed systems in Pilot-PSI G. De Temmerman a, K. Bystrov a, L. Marot b, M. Mayer c, J.J. Zielinski.
6 th EU PWI TF Meeting Madrid, Oct. 2007 1 Tritium Inventory in ITER: Laboratory data and extrapolation from tokamaks Th Loarer, J Roth, S Brezinsek, A.

6 th EU PWI TF Meeting Madrid, Oct Tritium Inventory in ITER: Laboratory data and extrapolation from tokamaks Th Loarer, J Roth, S Brezinsek, A.
1 PWI - related work at VR Marek Rubel (VR) Projects within ILW : Beryllium coatings for inner wall cladding (with MEC, UKAEA, FZJ, UCSD, TEKES) Development.

1 PWI - related work at VR Marek Rubel (VR) Projects within ILW : Beryllium coatings for inner wall cladding (with MEC, UKAEA, FZJ, UCSD, TEKES) Development.
9 th ITPA Meeting on Divertor/SOL physics, May 7-10, 2007, Garching Improvements to the B2 wall model: coatings and layers X. Bonnin, M. Warrier, D. Coster.

9 th ITPA Meeting on Divertor/SOL physics, May 7-10, 2007, Garching Improvements to the B2 wall model: coatings and layers X. Bonnin, M. Warrier, D. Coster.

Similar presentations

Ads by Google