Nuclear reactor plant with pressurized water reactor secured against

Abstract

In a nuclear reactor installation secured against rupture and having a pressurized water reactor, a straight-tube steam generator having a central ascending pipe, a coolant pump and lines connecting them in a primary circulatory loop, the coolant pump being installed in a primary chamber of the steam generator and forming with the latter a structural unit, the primary loop having hot and cold lines between a pressure vessel enclosing the reactor and the primary side of the steam generator, at least part of the hot and cold lines being united along the direction of their fluidic flow paths, the structural unit formed of the pump and the steam generator being upright with relatively short, straight and horizontal primary loop lines, and sheathing protective against rupture enclosing the pump, the steam generator and the lines of the primary loop, a tube bundle having a central passageway trough which the ascending pipe extends, an inlet chamber communicating with the top of the tube bundle, an outlet chamber communicating with the bottom of the tube bundle, tube support plates holding the bottom and top of the tube bundle, the ascending pipe feeding primary medium to the inlet chamber from which the primary medium is returned through the tube bundle to the outlet chamber, and a guidance elbow having a 90.degree.-bend extending through the outlet chamber, the guidance elbow connecting the ascending pipe and the hot line, the cold line communicating with the outlet chamber.