It is foreseen that the next step tokamak fusion experiment (ITER) will operate in improved confinement regimes such as the H-mode. H-mode is characterised by a spontaneous confinement transition that leads to an increase in plasma density and temperature, when the plasma heating power exceeds a given threshold. H-mode confinement is obtained mostly in divertor plasmas, i.e. in configurations with the magnetic separatrix inside the vacuum vessel, either two("double null configuration") or one ("single null configuration") poloidal field nulls. Transitions to H-mode have been also observed in limiter plasma configurations. These observations have been reported in several tokamaks, such as TFTR, TEXT-U and JIPP T-IIU Tokamaks. H-mode confinement transitions have been also recently observed in JET inner wall limiter plasmas and the confinement properties of these plasmas are analysed in this paper.