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Measurement of heat flux deposition on the main plasma facing components is an essential issue for safety and also to validate models that describe transport of particles and energy in the scrape of layer. The procedure to deduce the heat flux from the IR surface temperature measurements is often complicated by the presence of the surface layer of low thermal conductivity resulting in a higher temperature for a given flux. The presence of the surface layer is also matter of concern considering the edge plasma wall interaction, as a potential source or sink of particles. We propose here to visualize the deposited layer on the Toroidal Pump Limiter using IR data during disruptions. The area size and shape are, and this is the main advantage of using IR data during disruptions, investigated during the experimental campaigns.

Additional information

Authors: CORRE Y et al, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR)
Bibliographic Reference: An oral paper given at: 32nd EPS Conference on Controlled Fusion and Plasma Physics Organised by: Asociación EURATOM-CIEMAT para Fusión Held at: Congress Palace of Tarragona, Tarragona (ES)
Availability: Available from Association EURATOM-CEA, Departement de Recherches sur la Fusion Controlee, CEA Cadarache, F-13108 St Paul-Lez-Durance, FranceL%Tel: (+33) 4 42 25 70 01; Fax: (+33) 4 42 25 64 21 E-mail:
Record Number: 200518292 / Last updated on: 2005-07-26
Original language: en
Available languages: en
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