Article Dans Une Revue Fusion Engineering and Design Année : 2015

Design and preliminary thermal validation of the WEST actively cooled upper divertor

Résumé

Design of WEST upper divertor target, regarding integration and thermal load specifications.

• The proposed concept enables to sustain in steady state, at least, a maximum heat flux of 8 MWm -2 .

• The plasma incident surface is covered with a <30 m thick W coating.

• HHF tests up to 10.5 MWm -2 were successfully performed on the upper divertor prototype.

• Upper divertor targets will be fabricated and installed in the vacuum chamber in 2015.

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Dates et versions

cea-04738409 , version 1 (15-10-2024)

Identifiants

Citer

M. Richou, M. Missirlian, D. Guilhem, M. Lipa, P. Languille, et al.. Design and preliminary thermal validation of the WEST actively cooled upper divertor. Fusion Engineering and Design, 2015, 98-99, pp.1394 - 1398. ⟨10.1016/j.fusengdes.2014.12.017⟩. ⟨cea-04738409⟩
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