Steam generator and pressurized-water nuclear reactors

Steam generator for pressurized-water nuclear reactors having a steam jacket, two horizontally disposed tube support plates, a multiplicity of rectilinear tubes traversed by primary water, the tubes being disposed within the steam jacket secured between the two tube support plates, a compensator for length equalization, and at least one connecting tube for supplying the primary water secured within the steam jacket through the compensator, comprising a water chamber respectively disposed within the steam jacket and adjoining each of the tube support plates, and a guide jacket for circulating feedwater supplied into the steam jacket, the guide jacket being mounted within the steam jacket and having a lower portion extending into a space located between the steam jacket and the lower tube support plate.