Abstract: The invention relates to a hydrodynamic converter comprising a torus-shaped working chamber surrounding the converter axis, said chamber having the form of a ring channel in an axial cross-section; an impeller which is rotationally fixed to an input shaft; a turbine wheel which is rotationally fixed to an output shaft, and a ring of adjustable guide vanes. The converter is designed in such a way that it has a lambda value of less than 0.0005.

Abstract: A primary recirculating pump for pressurized water or boiling water nuclear reactors has a spherical housing with a radially extending integral outlet, a rotary impeller which is insertable or removable through a sealable opening of the housing, and a composite inlet including an outer section which is integral with the housing and a discrete inner section which is insertable and removable through the opening and serves to convey to the impeller, and to preferably accelerate, the fluid which enters through the outer section. The inner section may resemble a bend or a funnel which diverges from the impeller toward the outer section, and the outer section may resemble a bend, a substantially straight pipe which extends tangentially of the housing, or a helical or semihelical conduit. The plane of the outer section is closely adjacent to or even coincides with the plane of the outlet, especially when the outer section is tangential to the housing or resembles a portion of or an entire helix.

Abstract: A nuclear steam supply system wherein each of a plurality of centrifugal pumps begins to operate with full cavitation in response to an abrupt drop of system pressure in the event of leakage. This is achieved by influencing a net positive suction head of each pump over the entire range of fluid flow and/or by influencing the net positive suction head upstream of the pumps. The first mode of causing the pumps to operate with full cavitation includes an appropriate selection of the inlet angle and/or inlet diameter of the pump impeller, the provision of auxiliary stationary guide wheels which are located upstream of the pumps and can circulate the fluid in or counter to the direction of rotation of the respective pump impellers, or the provision of suitably curved guide vanes in the pumps. The second mode includes interrupting the admission of undercooled fluid into the system upstream of the pumps.

Abstract: A primary recirculating pump for pressurized water or boiling water nuclear reactors has a spherical housing with a radially extending integral outlet, a rotary impeller which is insertable or removable through a sealable opening of the housing, and a composite inlet including an outer section which is integral with the housing and a discrete inner section which is insertable and removable through the opening and serves to convey to the impeller, and to preferably accelerate, the fluid which enters through the outer section. The inner section may resemble a bend or a funnel which diverges from the impeller toward the outer section, and the outer section may resemble a bend, a substantially straight pipe which extends tangentially of the housing, or a helical or semihelical conduit. The plane of the outer section is closely adjacent to or even coincides with the plane of the outlet, especially when the outer section is tangential to the housing or resembles a portion of or an entire helix.

Abstract: A nuclear steam supply system wherein each of a plurality of centrifugal pumps begins to operate with full cavitation in response to an abrupt drop of system pressure in the event of leakage. This is achieved by influencing the net positive suction head of each pump over the entire range of fluid flow and/or by influencing the net positive suction head upstream of the pumps. The first mode of causing the pumps to operate with full cavitation includes an appropriate selection of the inlet angle and/or inlet diameter of pump impeller, or the provision of suitably curved guide vanes in the pumps. The second mode includes interrupting the admission of undercooled fluid into the system upstream of the pumps.

Abstract: A nuclear steam supply system wherein each of a plurality of centrifugal pumps begins to operate with full cavitation in response to an abrupt drop of system pressure in the event of leakage. This is achieved by influencing the net positive suction head of each pump over the entire range of fluid flow and/or by influencing the net positive suction head upstream of the pumps. The first mode of causing the pumps to operate with full cavitation includes an appropriate selection of the inlet angle and/or inlet diameter of the pump impeller, the provision of auxiliary impellers which are located upstream of the pumps and can circulate the fluid in or counter to the direction of rotation of the respective pump impellers, or the provision of suitably curved guide vanes in the pumps. The second mode includes interrupting the admission of undercooled fluid into the system upstream of the pumps.