The WEST project: Current status of the ITER-like tungsten divertor

[1]  C. Gil,et al.  The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment , 2014 .

[2]  J. Bucalossi,et al.  Developments Toward Fully Metallic Actively Cooled Plasma-Facing Components for the Tungsten Divertor in ITER , 2013 .

[3]  Frederic Escourbiac,et al.  ITER tungsten divertor design development and qualification program , 2013 .

[4]  P. Languille,et al.  The WEST project: PFC shaping solutions investigated for the ITER-like W divertor , 2013 .

[5]  Frederic Escourbiac,et al.  The WEST programme: Minimizing technology and operational risks of a full actively cooled tungsten divertor on ITER , 2013 .

[6]  J. Bucalossi,et al.  Design, integration and feasibility studies of the Tore-Supra West divertor structure , 2013 .

[7]  C. Reux,et al.  Modelling of Power Deposition on the JET ITER-Like Wall using the Code PFCFLUX , 2013 .

[8]  M. Sugihara,et al.  A full tungsten divertor for ITER: Physics issues and design status , 2013 .

[9]  P. Gavila,et al.  The heat removal capability of actively cooled plasma-facing components for the ITER divertor , 2011 .

[10]  B. Riccardi,et al.  High heat flux testing of mock-ups for a full tungsten ITER divertor , 2011 .

[11]  Sylvain Brémond,et al.  Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing , 2011 .

[12]  B. Riccardi,et al.  Fatigue lifetime of repaired high heat flux components for ITER divertor , 2011 .

[13]  F. Escourbiac,et al.  Development of Actively Cooled Plasma-Facing Components for Tore Supra , 2009 .

[14]  H. Greuner,et al.  Fabrication and testing of W7-X pre-series target elements , 2007 .