The heat removal capability of actively cooled plasma-facing components for the ITER divertor - CEA - Commissariat à l’énergie atomique et aux énergies alternatives
Article Dans Une Revue Physica Scripta Année : 2011

The heat removal capability of actively cooled plasma-facing components for the ITER divertor

Résumé

Non-destructive examination followed by high-heat-flux testing was performed for different small-and medium-scale mock-ups; this included the most recent developments related to actively cooled tungsten (W) or carbon fibre composite (CFC) armoured plasma-facing components. In particular, the heat-removal capability of these mock-ups manufactured by European companies with all the main features of the ITER divertor design was investigated both after manufacturing and after thermal cycling up to 20 MW m -2 . Compliance with ITER requirements was explored in terms of bonding quality, heat flux performances and operational compatibility. The main results show an overall good heat-removal capability after the manufacturing process independent of the armour-to-heat sink bonding technology and promising behaviour with respect to thermal fatigue lifetime under heat flux up to 20 MW m -2 for the CFC-armoured tiles and 15 MW m -2 for the W-armoured tiles, respectively.
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Dates et versions

cea-04724810 , version 1 (08-10-2024)

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Citer

Marc Missirlian, M Richou, B Riccardi, P Gavila, T Loarer, et al.. The heat removal capability of actively cooled plasma-facing components for the ITER divertor. Physica Scripta, 2011, 2011 (T145), pp.014080. ⟨10.1088/0031-8949/2011/T145/014080⟩. ⟨cea-04724810⟩
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