A control-oriented model of the current profile in tokamak plasmaEmmanuel Witrant, P. Moreau, E. Joffrin et al.|Plasma Physics and Controlled Fusion|2007Cited by 117
Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testingJ. Bucalossi, A. Saille, A. Argouarch et al.|Fusion Engineering and Design|2011Cited by 70
Validation of the ITER-relevant passive-active-multijunction LHCD launcher on long pulses in Tore SupraA. Ekedahl, B. Saoutic, L. Delpech et al.|Nuclear Fusion|2010Cited by 60