1. Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing
- Author
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F. Faisse, S. Hacquin, X. Courtois, P. Monier-Garbet, J. Garcia, Patrick Maget, A. Argouarch, Yannick Marandet, T. Loarer, R. Magne, R.A. Pitts, M. Jouve, O. Baulaigue, Yann Corre, Marina Becoulet, Sylvain Brémond, L. Gargiulo, Ph. Cara, A. Martinez, Eric Nardon, B. Pégourié, P. Bayetti, P. Hertout, A. Ekedahl, V. Basiuk, Bernard Bertrand, Roland Sabot, G. T. A. Huysmans, James Paul Gunn, C. Grisolia, P. Moreau, Marc Missirlian, M. Chantant, M. Joanny, O. Meyer, M. Richou, G. Jiolat, Didier Mazon, S. Lisgo, L. Jourd’heuil, Frederic Imbeaux, Jérôme Bucalossi, M. Lipa, A. Saille, E. Tsitrone, A. Simonin, A.S. Kukushkin, F. Samaille, C. Portafaix, S. Panayotis, F. Saint-Laurent, M. Firdaouss, L. Doceul, and C. Gil
- Subjects
Materials science ,Tokamak ,Mechanical Engineering ,Divertor ,Nuclear engineering ,chemistry.chemical_element ,Blanket ,Tore Supra ,Tungsten ,Heat sink ,law.invention ,Nuclear Energy and Engineering ,Heat flux ,chemistry ,law ,Limiter ,General Materials Science ,Civil and Structural Engineering - Abstract
In order to reduce the risks for ITER Plasma Facing Components (PFCs), it is proposed to equip Tore Supra with a full tungsten divertor, benefitting from the unique long pulse capabilities, the high installed RF power and the long experience with actively cooled high heat flux components of the Tore Supra platform. The transformation from the current circular limiter geometry to the required X-point configuration will be achieved by installing a set of copper poloidal coils inside the vacuum vessel. The new configuration will allow for H-mode access, providing relevant plasma conditions for PFC technology validation. Furthermore, attractive steady-state regimes are expected to be achievable. The lower divertor target design will be closely based on that currently envisaged for ITER (W monoblocks), while the upper divertor region will be used to qualify the main first wall heat sink technology adopted for the ITER blanket modules (CuCrZr copper/stainless steel) with a tungsten coating (in place of the Be tiles which ITER will use). Extended plasma exposure will provide access to ITER critical issues such as PFC lifetime (melting, cracking, etc.), tokamak operation on damaged metallic surfaces, real time heat flux control through PFC monitoring, fuel retention and dust production.
- Published
- 2011
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