5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

P4.101 High heat flux testing of newly developed tungsten components for WEST

8 Sep 2016, 14:20
1h 40m
Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Foyer 2A (2nd floor), 3A (3rd floor)

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 101
Poster F. Plasma Facing Components P4 Poster session

Speaker

G. Pintsuk (Forschungszentrum Jülich GmbH)

Description

The WEST (W -for tungsten- Environment in Steady-state Tokamak) project is based on an upgrade of Tore Supra tokamak. ITER-like actively cooled tungsten targets (monoblocks) will be integrated in the lower divertor and a new set of actively cooled tungsten coated plasma facing components will cover a part of the vessel to provide a fully metallic environment. In preparation of the production of the actively cooled tungsten targets for the lower divertor the qualification of suppliers is done by exposing small-scale mock-ups to cyclic high heat flux tests in the electron beam facility JUDITH 1 at Forschungszentrum Jülich. Thereby, the small-scale mock-ups are based on the ITER design, consisting of 7 monoblocks mounted on a CuCrZr cooling tube and connected via a soft Cu-interlayer. The results presented herein focus on the high heat flux test results of two mock-ups produced by ASIPP in China. The testing was performed by thermal cycling at 10 MW/m22 and at 20 MW/m22. While for the first component failure occurred after 769 cycles at 10 MW/m22 due to accidental conditions in the testing facility, the second component, being pre-exposed on two blocks to 700 cycles at 10 MW/m22, survived 500 additional cycles at 10 MW/m2 and up to 500 cycles at 20 MW/m22 without obvious damage formation. The discussion of the results comprises the thermal performance of the mock-ups during thermal cycling in relation to the initial qualification via infrared thermography facility SATIR at CEA-Cadarache, the tungsten thickness as well as the subsequent microstructural analyses. The latter focus on the most important issues determined in earlier studies on ITER qualification mock-ups and components, i.e. tungsten recrystallization and macro-crack formation, the integrity of the CuCrZr cooling tube, and plastic deformation induced changes in the pure Cu-interlayer.

Co-authors

D. Guilhem (CEA, IRFM, F-13108 Saint-Paul-Lez-Durance, France) G. Pintsuk (Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), 52425 Jülich, Germany) G.-N. Luo (Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP), Hefei, Anhui, China) J. Bucalossi (CEA, IRFM, F-13108 Saint-Paul-Lez-Durance, France) M. Missirlian (CEA, IRFM, F-13108 Saint-Paul-Lez-Durance, France) Q. Li (Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP), Hefei, Anhui, China) W. Wang (Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP), Hefei, Anhui, China)

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