WEST Physics Basis. (6th May 2015)

• Record Type: Journal Article
• Authors: Bourdelle, C.; Artaud, J.F.; Basiuk, V.; Bécoulet, M.; Brémond, S.; Bucalossi, J.; Bufferand, H.; Ciraolo, G.; Colas, L.; Corre, Y.; Courtois, X.; Decker, J.; Delpech, L.; Devynck, P.; Dif-Pradalier, G.; Doerner, R.P.; Douai, D.; Dumont, R.; Ekedahl, A.; Fedorczak, N.; Fenzi, C.; Firdaouss, M.; Garcia, J.; Ghendrih, P.; Gil, C.; Giruzzi, G.; Goniche, M.; Grisolia, C.; Grosman, A.; Guilhem, D.; Guirlet, R.; Gunn, J.; Hennequin, P.; Hillairet, J.; Hoang, T.; Imbeaux, F.; Ivanova-Stanik, I.; Joffrin, E.; Kallenbach, A.; Linke, J.; Loarer, T.; Lotte, P.; Maget, P.; Marandet, Y.; Mayoral, M.L.; Meyer, O.; Missirlian, M.; Mollard, P.; Monier-Garbet, P.; Moreau, P.; Nardon, E.; Pégourié, B.; Peysson, Y.; Sabot, R.; Saint-Laurent, F.; Schneider, M.; Travère, J.M.; Tsitrone, E.; Vartanian, S.; Vermare, L.; Yoshida, M.; Zagorski, R.;
• Other Names: collab.
• Is Part Of: Nuclear fusion. Volume 55:Number 6(2015:Jun.)
• Publication Date: 2015-05-06
• Subjects: plasma facing components -- divertor -- tokamak -- plasma physics; Nuclear fusion -- Periodicals; 621.48405
• DOI: 10.1088/0029-5515/55/6/063017
• Languages: English
• ISSNs: 0029-5515

Abstract

Abstract: With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng. Des. 89 907–12 ), the Tore Supra facility and team expertise (Dumont et al 2014 Plasma Phys. Control. Fusion 56 075020 ) is used to pave the way towards ITER divertor procurement and operation. It consists in implementing a divertor configuration and installing ITER-like actively cooled tungsten monoblocks in the Tore Supra tokamak, taking full benefit of its unique long-pulse capability. WEST is a user facility platform, open to all ITER partners. This paper describes the physics basis of WEST: the estimated heat flux on the divertor target, the planned heating schemes, the expected behaviour of the L–H threshold and of the pedestal and the potential W sources. A series of operating scenarios has been modelled, showing that ITER-relevant heat fluxes on the divertor can be achieved in WEST long pulse H-mode plasmas.