Abstract: A steam generator in which the heat-carrying fluid is a liquid metal and the detection of leakages is carried out by sampling the liquid metal. The end of the steam generator through which the liquid metal enters comprises a tube plate (2), a thermal protection plate (10) and a hollow flow sill (22) constituting the end part of the bundle case (4). Tubes (20) for protecting the tubes (3) of the bundle are placed around each of the tubes (3) between the protection plate (10) and the tube plate (2), the space (17) between these two plates being closed on its periphery by a sleeve (15). The hollow sill (22) communicates with the space (17) through tubes (27) and with the inner volume or the bundle case (4). A liquid metal take-off device (31, 32) is placed in the hollow sill (22). The invention applies in particular to steam generators of fast neutron nuclear reactors cooled with liquid sodium.

Abstract: According to the invention, the central body (10) of the steam generator filled with liquid sodium in its upper and middle part comprises in its lower part, on one hand, a crowned end wall (23) under which an inert gas is injected for forming a pocket (24) which contains a small volume of gas and defines a gas-liquid separation surface (25) for the reflection and the attenuation of a pressure wave in the event of a sodium-water reaction, and, on the other hand, a spider element (11) which connects the lower end of the central body (10) to an end element (16) provided with a frustoconical portion (17) which extends with an annular clearance into the outlet pipe (5) for the liquid sodium which has travelled through the tube bundle (7). Application in particular to nuclear power stations.

Abstract: The invention relates to a secondary heat transfer circuit for a liquid metal-cooled nuclear reactor, as well as to a steam generator which can be used in such a circuit.According to the invention, a downstream buffer tank and an upstream buffer tank are arranged within the steam generator. The upstream buffer tank is annular and surrounds and communicates with an area of the generator by which the liquid metal flows downwards between the exchange zone and the discharge tube. The pressure of the neutral gas pocket in the downstream buffer tank is higher than that of the pocket of the upstream buffer tank.Application to fast neutron nuclear reactors.

Abstract: Steam outlet connection for connecting the outlet (5) of a tube of the bank of tubes of a steam generator to the pipe (8) connecting it to a steam header. The connection is of the T type with a straight portion (10) closed at one end and a side branch (19) connected to the pipe (8). The closed end of the straight portion (10) has an end wall (14) having a zone of sufficiently slight thickness to permit its perforation for the purpose of injecting a gas into the tube.

Abstract: A typical embodiment of the invention is a steam drying device that has a frame with two recessed slipways spaced from each other. A first array of longitudinally disposed bars within the frame are spaced transversely from each other. The ends of the bars in this first array, moreover, are received within respective slipway recesses. There also is a second array of longitudinal bars, the ends of which are received in respective slipways, the bars in both arrays being transversely spaced from each other to enable the bars to remove water droplets from the steam.