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FP7

Power flux in the ITER divertor tile gaps during ELMs

Funded under: FP7-EURATOM

Abstract

In order to withstand strong thermo-mechanical stress in the ITER's divertor, its plasma facing components will be castellated. Consequently, a larger area with complex geometry will be exposed to high fluxes coming from the plasma. In order to evaluate the possible damage caused by transient events, we present here calculations of the expected power loads in the ITER divertor tile gaps during ELMs. We use a self-consistent, two-dimensional particle-in-cell technique to model plasma deposition with realistic boundary conditions. The power loads on the tile surface and inside the gaps are investigated for various magnetic configurations of the strike point and strong plasma parameters.

Additional information

Authors: DEJARNAC R, Association EURATOM-IPP.CR, Prague 8 (CZ);KOMM M, Association EURATOM-IPP.CR, Prague 8 (CZ);PANEK R, Association EURATOM-IPP.CR, Prague 8 (CZ);GUNN J P, 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: 18th International Conference on Plasma-Surface Interactions in Controlled Fusion Device Organised by: Laboratorio Nacional de Fusión Held in: Toledo (ES)
Availability: This article can be accessed online by subscribers, and can be ordered online by non-subscribers, at: http://dx.doi.org/doi:10.1016/j.jnucmat.2009.01.216
Record Number: 200910347 / Last updated on: 2009-09-22
Category: PUBLICATION
Original language: en
Available languages: en
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