Steam generator and pressurized-water nuclear reactors

摘要

Steam generator for pressurized-water nuclear reactors having a steam jacket wherein a multiplicity of rectilinear tubes traversed by primary water is secured between two horizontally disposed tube support plates, and at least one connecting tube for supplying the primary water is secured to the steam jacket through a compensator for length equalization, includes a water chamber respectively disposed within the steam jacket and adjoining each of the tube support plates, and a guide jacket for circulating feed-water 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.