H. Dougnac

The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment

C. Gil, C. Bourdelle, J. Bucalossi, 2014 .

Contribution of Tore Supra in preparation of ITER

C. Laviron, D. Ciazynski, B. Lacroix, 2011 .

Design and test program of a simplified divertor dummy coil structure for the WEST project

J. Bucalossi, D. Keller, S. Larroque, 2013 .

Progresses on WEST Platform Construction towards First Plasmas

C. Gil, C. Bourdelle, Y. Camenen, 2017 .

Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation

Liang Wang, T. Salmon, A. Diallo, 2021, Nuclear Fusion.

70 keV neutral hydrogen beam injector with energy recovery for application in thermonuclear fusion research

P. Fazilleau, H. Dougnac, A. Simonin, 2002 .

Science and technology research and development in support to ITER and the Broader Approach at CEA

J. B. Lister, B. Lacroix, L. Zani, 2013 .

Performance and design definition of the WEST Tokamak divertor coils power supplies

E. Nardon, H. Dougnac, N. Dumas, 2015, 2015 IEEE 26th Symposium on Fusion Engineering (SOFE).

Investigation of steady-state tokamak issues by long pulse experiments on Tore Supra

C. Laviron, D. Ciazynski, B. Lacroix, 2009 .